ML17214A234

Proposed Tech Specs Revising Requirement for Primary & Secondary Coolants in Steam Generator to Be Greater than 100 F When Coolant Pressure Greater than 200 Psig

ML17214A234
Person / Time
Site:	Saint Lucie
Issue date:	06/17/1983
From:	FLORIDA POWER & LIGHT CO.
To:
Shared Package
ML17214A236	List: ML17214A234 ML17301A044
References
NUDOCS 8306210169
Download: ML17214A234 (11)

Text

3/4.4'REACTOR COOLANT SYSTEM 3/4.4;1 REACTOR COOLANT LOOPS AND COOLANT CIRCULATION STARTUP AND POWER OPERATION LIMITING CONDITION FOR OPERATION 3.4.l.1 Both Reactor Coolant loops and both Reactor Coolant pumps in each loop shall be in operation.

APPLICABILITY:

1 and 2." ACTION: With less than the above required Re'actor Coolant pumps in operation, be in at least HOT STANDBY within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.'URVEILLANCE RE UIREMENTS 4.4.1.1 The above required Reactor Coolant loops shall be verified to be in operation and circulating Reactor Coolant at least once per 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> s.See Special Test Exceptions 3.10.3.--:-

830h21 0169 830617 PDR ADOCK 05000389'PDR't ST.LUCIE-UNIT 2 3/4 4-1 AMENDMENT NO.

I l I ,4r u

~~PLANT SYSTEMS MAIN FEEDWATER LINE ISOLATION VALVES LIMITING CONDITION FOR OPERATION 3.7.1.6 Each main feedwater line isolation valve shall be OPERABLE.APPLICABiLITY:

MODES 1, 2, 3, and 4.ACTION: MODE 1 MODES 2, 3-and 4 With one main feedwater line isolation valve inoperable but open, POWER OPERATION may continue provided the inoperable valve is restored to OPERABLE status within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />;otherwise, be in at least 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 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.With one main feedwater line isolation valve inoperable, subseqent operation in MODE 2, 3, or 4 may proceed provided: a.The isolation valve is maintained closed.b.The provisions of Specification 3.0.4 are not applicable.

-~Otherwise, be in at least 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 COL'D SHUTDOWN'wi'thin the following 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.SURVEILLANCE RE UIREMENTS 4.7.1.6 Each main feedwater line isolation valve shall be demonstrated OPERABLE by: a.Part-stroke exercising the valve at.least once per 92 days, and b.Verifying full closure within 4.2 seconds on any closure actuation signal while in HOT STANDBY with T>515 F during each reactor shutdown except that verification B full closure within="4, 2-seconds need not be determined more often than once per 92 days.ST.LUCIE" UNIT 2 3/4 7-10 AMENDMENT NO.'

PLANT SYSTEMS 3/4 7-12 STEAM GENERATOR PRESSURE/TEMPERATURE LIMITATION LIMITING CONDITION FOR OPERATION 3.7.2 The temperature of the secondary coolant in the steam generators shall be greater than 100'F when the pressure of the secondary coolant in the steam generator is greater than-200psig.APPLICABIlITY:

At all times.ACTION: Wi th the requiranents of the above speci fication not satisfied:

a.Reduce the steam generator pressure to less than or equal to 200 psig within 30 minutes, and b.Perform an engineering evaluation to determin'e the effect of the overpressurization on the structural integrity of the steam.generator.

Determine that the steam generator remains acceptable for continued operation prior to increasing its temperatures above 200'F.SUR VE I LLANC E R EQU IR EME NTS 4.7.2 The pressure of'the secondary side of the steam generators shall be determined to be less than 200 psig at least once per hour when the temperature of secondary coolant is less than 100 F.ST.LUCIE-UNIT-.2 3/4 7-12 AMENDMENT NO.

PLANT SYSTEMS 3/4.7.'ll FIRE SUPPRESSION SYSTEMS FIRE SUPPRESSION WATER SYSTEM"'I LIMITING CONDITION FOR OPERATION 3.7.11.1 The fire suppression water system shall be OPERABLE with: a.Two fire suppression pumps, each with a capacity of 2350 gpm, with their discharge aligned to the fire suppression header, b.Separate water supplies, each.with a minimum contained volume of 300,000 gallons,.and C.An OPERABLE flow path capable of taking suction from the city water storage tank lA and the city water storage tank 1B and transferring the water through distribution piping with OPERABLE sectionalizing control or isolation valves to the yard hydrants, the last valve ahead of the water flow alarm device on each sprinkler or hose standpipe required to be OPERABLE per Specifications 3.7.11.2, 3.7.11.3 and 3.7.11.4.APPI ICABILITY:

At al 1 times.ACTION: a.b.With one pump and/or one water supply inoperable,,restore the inoperable equipment to OPERABLE status within 7 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 plans and procedures to be used to restore the inoperable equipment to OPERABLE status or to provide an alternate backup pump or supply.The provisions of Specifications 3.0.3 and 3'.4 are not applicable.

With the'fire suppression water system otherwise inoperable, 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 />.This system is shared between St.Lucie Units 1 and 2.ST.LUCIE",UNIT 2 3/4 7"30 AMENDMENT.

NO~

PLANT SYSTEMS BASES 3/4.7.1.7 ATMOSPHERIC DUMP VALVES'he limitation on maintaining the atmospheric dump valves in the manual mode of operation is to ensure the atmospheric dump valves will be closed in the event of a steam line break.'or the steam line break with atmospheric

.dump valve control failure event, the failure of the atmospheric dump valves to close would be a valid concern were the system to be in the automatic mode during power operations.

3/4.7.2 STEAM GENERATOR PRESSURE/TEMPERATURE LIMITATION The limitation

'on steam generator pressure and temperature ensures that-'he pressure-induced stresses in the steam generators do not exceed the maximum allowable fracture toughness stress limits.The limitations to lOO~F and 200 psig are based on a steam generator RTNDT of 20 F and are sufficient to prevent brittle fracture.3/4.7.3 COMPONENT COOLING WATER SYSTEM The OPERABILITY'f the Component Cooling Water System ensures that sufficient'ooling capacity is available for.continued operation of-safety-related equipment during normal and accident-conditions.

The redundant cooling capacity of this system,.assuming a single failure,'~""is consistent with the:assumptions used in the safety analyses.'/4.7.4 INTAKE COOLING WATER SYSTEM The OPERABILITY of the Intake Cooling Water System ensures that sufficient cool.ing capacity's available for-continued

'operation of equipment during n'ormal.and accident conditions.

The redundant cooling capacity of this system, assuming a single failure, is consistent with the assumptions used in'the safety analyses.ST.LUCIE-UNIT 2 B 3/4 7-4 AMENDMENT NO.

ADMINISTRATIVE CONTROLS SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT" 6.9.1.10 Routine Radioactive Effluent Release Reports covering the operation of the unit during the previous 6 months of operation shall be submitted within 60 days after January 1 and July 1 of each year.The period of the first report shall begin with the date of initial criticality.

The Radioactive Effluent Release Reports shall include a summary of the quantities of radioactive liquid and gaseous effluents and solid waste releaseQ from the unit as outlined in Regulatory Guide 1.21,"Measuring, Evaluating, and'Reporting Radioactivity in Solid Wastes and Releases of Radioactive Materials in Liquid and Gaseous Effluents form Light-Mater-Cooled Nuclear Power Plants," Revision 1, June 1974, with data summarized on a quarterly basis following the format of Appendix B thereof.The Radioactive Effluent Release Report to be submitted within 60 days after January'of each year shall.include an annual summary of hourly meteorological data collected over the previous year.This annual summary'ay be either in the form of an hour-by-hour li.sting on magnetic tape of wind speed, wind direction, atmospheric stability, and precipitation (if measured), or in the form of joint frequency distiibutions of wind speed, wind direction, and atmos-pheric stability.

• " This same report shall include an assessment of the radiation doses due to the radioactive liquid and gaseous effluents released from the unit or station during the previous calendar year.This same report shall also include an assessment of the radiation doses from radioactive liquid and gaseous effluents to MEMBERS OF 3;HE,.PUBLIC due to their activi.ties inside the SITE BOUNDARY (Figure 5.1-1)during the report period.All assump-tions used in making.,these assessments, i.e:, specific'acti,vity., exposure time and location, shall be included in these reports..The meteorological condi-tions concurrent with the time of release of radioactive materials in gaseous effluents, as determined by sampling frequency and measurement, shall be used for determi'ning the gaseous pathway doses.The assessment of radiation doses shall be performed in accordance with the methodology and parameters in the OFFSITE DOSE CALCULATION MANUAL (ODCH)..Every 2 years using the previous 6 months release history for isotopes and historical meteorolgical data determine the controlling age group for both liquid and gaseous pathways.If changed from current submit change to ODCH to reflect new tables for these groups and use the new groups in subsequent dose calculations.

The Radioactive Effluent Release Report to be submitted 60 days after January 1 of each year shall also include an assessment of radiation doses to the likely most exposed MEMBER OF THE PUBLIC from reactor releases for the previous~A single submittal may be made for a multiple'unit station.The submittal should combine those sections that are common to all units at the station;however, for units with separate radwaste systems, the submittal shall specify the releases of radioactive material from each unit.In lieu of submission with the-.-Radioactive..Effluent Release~"',.-.-Repor.'t'the licensee has the option of retaining this summary of required meteorological data on site in a file that shall be provided to the NRC upon request.ST.LUCIE" UNIT 2 6-20 AMENDMENT NO.

0 STATE OF FLORIDA))ss.COUNTY OF PALM BEACH)B.L.Dad, being first duly sworn, deposes and says: That he is Vice President of Florida Power 6 Light Company, the Licensee herein;That he has executed the foregoing document;that the statements made in this document are true and correct to the best of his knowledge, information, and belief, and that he is authorized to execute the document on behalf of said Licensee.~,~A B.L.Dady Subscribed and sworn to before me this~I'J'/'7.c', day of , I983.['~!r<NOTARY BLIC, in and for the County';,",of, Palm Beach, State of Florida.Notary Pob)ic, State of Ronda at Largo My commission expires: Bonding Agancy F P l4@~V 1'4 r r~"e'I 8'I