ML17341A537

Technical Evaluation of Response to Position 5 of Item II.E.4.2 of NUREG-0737 Containment Isolation Setpoint for Turkey Point Nuclear Power Station.

ML17341A537
Person / Time
Site:	Turkey Point
Issue date:	05/30/1981
From:	Gilmore L, Ruvalcaba W EG&G, INC.
To:
Shared Package
ML17341A532	List: ML17341A535 ML17341A537
References
RTR-NUREG-0737, RTR-NUREG-737, TASK-2.E.4.2, TASK-TM SRO-277, NUDOCS 8109180218
Download: ML17341A537 (10)

Text

Knergy l4easurernents Group San Ramon Operations, SRO-277 Nay 1981 TECHNICAL: EVALUATION Of THE RESPONSE TO POSITION NO-5 OF I,TEN II:. E'. 4'.2 OF NUREG-0737 CONTA'I NMENT ISO LATION SETP OINT FOR THE TURKEY POINT NUCLEAR POWER PLANT UNITS G.AND 4 (DOCKET Noa. 50-250 and 50- 254) by W.. 0. Wade Approved for Puolication M. R. Ruvalcaoa Oepartment Hanager This; document is UNCLASSIF.IEO Oerivative.

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L.. W., Gilmore.

Operations. Manager Work Performed~for LawrenceiLivermore National Laboratory under U.S'. Department of'Energy, Contract No. DE'-ACO8-76,NVO'1083..

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INTRODUCTION AND BACKGROUND As a consequence of the incident at TMI-2, implementation of a number of new requirements has been recommended for operating new requirements are described in NUREG-0650, "NRC 'Action PTan Devel-reactors.'hese oped as a Result of the TMI-2 Accident," Hay 1980, and NUREG-0737, "Clari- ,

fication of THI Action Plan Requirements," November 1980. The NRC staff has also requested l.icensees to submit information sufficient to permit an independent evaluation of their response to these new requirements. This repor provides an evaluation of the response to Action Plan Item II.E'.4.2, position 5, by the designated licensee.

DESIGN BASIS OR REVIE'A CRITERIA Position 5 requires that the containment pressure setpoint that initiates containment isolation for non-essential system containment vessel penetrations be at, or reduced to, "...the minimum compatible with normal operating conditions."

TECHNICAL EVALUATION Response evaluation is based upon the values provided for the following parameters:

(I) The maximum observed or expected containment pressure during normal operation.

(2) The loop error and observed drift in the. pressure sensing instrumentation providing the isolation signal (see note).

(3) The containment isolation pressure setpoint.

NOTE': The clarification document (NUREG-0737) provided only the 'expected margin for instrument error and, did not specify acceptable values for instrument drift or atmospheric. changes, contributing to the total sensing loop error., Additional staff guidance, established: a l.i'mit; of 3.0. psi for an isolation setpoint margin over the. normal containment: pressure to: account for total loop error. I'- addition, for subatmospheric contain- .

ments:, a. 3'.0.'si setpoint. margin over atmospheric; pressure, is: also cons,idered acceptable; In consideration of-'hese values,, the. iso,lation pressure setpoint is; to; be as, low as; practical without increasing the probability of inadver-tent. activation of-'he. isolation signal'..

CONCLUSIONS; The. letters. dated. April 2'nd: 7,, L981', submitted: by FTorida, Power and Light: Company,. provided: sufficient, information to concl'ude that; the containment: isolation: pressure setpoint: for Turkey: Pbint; Nucl'ear Power Plant, Units:, 3'nd. 4',, meets, the: NUREG'-0660/0737.'equirements. and, is, within the additional limiting guidelines, provided. by the NRC: staff;

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ENCLOSURE 7 CONTAINMENT SYSTEMS LIMITING CONDITION FOR OPERATION 3.6. 1'.7 The containment purge supply and exhaust isolation valves may be open for safety-related reasons [or shall be locked closed1. The containment vent line isolation valves may be open for safety-related reasons [or shall be. locked closed].

APPLICABILITY: MODES 1, 2, 3, and 4.

ACTION:.

7For plants with valves closed by technical specification)

With one containment purge supply and/or one exhaust isolation valve open, close the open valve(s) within one hour or 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 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.,

(For plants with valves that may be opened: by technical specifications) 1; With one containment purge supply and/or one exhaust isol'ation or vent valve inoperable, close the associated OPERABLE valve and either restore the inoperable valve to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or lock the OPERABLE valve closed.

2. Operation may then continue until performance of the next required valve test provided that the OPERABLE valve is verified to be locked closed at least once per 31 days..

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3. Otherwise,, be in at least; HOT STANDBY within the next six hours: and in COLD .SHUTDOWN wi thin the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

4. The provisions. of Specification 3.0.4 are not applicable.

SURVEILlANCE'EQUIREMENTS 4.6.,1..7;.1 The -inch containment purge supply and, exhaust: isol'ati'on valves-and the -incWvent'ine i:solation valves, shall be. determined locked closed; at least. once. per 31'ays..

4.6'..1.,7.2'he valve seals of the. purge supply: and exhaust isolation valves and, the vent. 1'ine. isol'ation: valves, shall be replaced. at: least. one pen .

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! %A I CONTAINMENT SYSTEMS 3/4 4.6.3 CONTAINMENT ISOL'ATION VALVES LIMITING CONDITION FOR OPERATION 3.6.3 The containment isolation valves specified in Table 3.6-1 shall be OPERABLE with isolation times as shown in Table 3.6-1.

APPLICABILITY: MODES 1, 2, 3 and 4..

ACTION:

With one or more of the isolation valves(s) specified in Table 3.6-1 inoperable, maintain at least one isolation valve OPERABLE in each affected penetration that is open and either:

a. Restore the inoperable valve(s) to OPERABLE status within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> or

b. Isolate each affected penetration within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> by use of at least one deactivated automatic valve. secured in the isolation position, or'.

Isolate each affected penetration within 4 hours by use of at. least one closed manual val.ve or blind flange;, or

d. Be in at'east HOT STANDBY within the next 6 hours and 'in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

SURVEILLANCE RE(}UIREMENXS 4.6.3.1 The isolation valves specified in Table 3.6-1 shall'e demonstrated OPERABLE prior to returning the: valve to service after maintenance, repair or repl'acement work is'erformed, on the valve: or i.ts associated actuator, control'r power. circuit by performance of a cycling test, and verification of: isol'a-tion time.

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~ '~' ~ CONTAINMENT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) 4.6.3.2 Each isolation valve specified in Table 3.6-1 shall be demonstrated OPERABLE during the COLD-SHUTDOWN or REFUELING MODE at least once per 18 months by:

a., Verifying that on a Phase A containment isolation test signal, each Phase A isolation valve actuates to its isolation position.

b. Verifying that on a Phase 8 containment isolation test signal, each Phase B isolation valve actuates to its isolation position.

4.6.3.3 The isolation time of each power operated or automatic valve .of Table 3.6-1 shall be determined to be within its limit when tested pursuant to Speci'fication 4.0.5.

4.6.3.4 The containment purge and vent isolation valves shall be demonstated OPERABLf at intervals not to exceed months.. Valve, OPERABILITY shall be determined by verifying that when the measured 1'eakage rate is added to the leakage rates determined pursuant to Specification 4.6.1.2.d for all other Type B and C penetration, the combined leakage rate is less than or equal to 0.60La.

However, the leakage rate for the containment purge and vent isolation valves shall be compared to the previously measured leakage rate to detect excessive valve degradation.

3/4 6-15

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