ML19341D711

Proposed Tech Specs 3.6 Re Drywell Sump Monitoring Sys. Util Safety Evaluation Supporting Change Encl

ML19341D711
Person / Time
Site:	FitzPatrick
Issue date:	04/03/1981
From:	POWER AUTHORITY OF THE STATE OF NEW YORK (NEW YORK
To:
Shared Package
ML19341D709	List: ML19341D708 ML19341D710 ML19341D711
References
NUDOCS 8104080474
Download: ML19341D711 (5)

Text

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ATTACHMENT I I

> PROPOSED TECHNICAL SPECIFICATION CHANGE 1

2 RELATED TO l DRYWELL SUMP MONITORING SYSTEM i

i l-POWER AUTHORITY OF THE STATE OF NEW YORK JAMES A. FITZPATRICK NUCLEAR POWER PLANT j

DOCKET NO. 50-333 APRIL 3 , 1981 I. .

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3.6 (cont'd) JAF 4.6 (cont'd)

4. . Except as specified in

-3.6.C.3 above, the reactor coolant water shall not exceed the following limits with steaming ~ rates greater than or equal to 100,000 lb/hr and during reactor shutdotins.

Conductivity 5 pmho/cm Chloride ion'O.5 ppm ,-

5. If Specification 3.6.C cannot be met, the reactor shall be placed in a cold condition within 24 hr.

D. Coolant Leakage D. Coolant Leakage

1. Any time irradiated fuel is in Reactor coolant leakage rate inside the primary the reactor vessel and reactor containment shall be established once/ day coolant temperature is above utilizing the Equipment and Floor Drain 212 F, reactor coolant leakage Samp Monitoring Systems.

into the primary containment l-from unidentified sources shall

.not exceed 5 gpm. In addition, the total reactor coolant

, system leakage into the primary containment shall not exceed i 25 gpm.

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2. The Drywell Sump Monitoring System shall be operable during reactor power operation.

a. From and after the time that either the equipment drain sump monitoring, or the floor drain sump monitoring subsystems is made or found to be tnoperable for any reason, l

j Amendment No. )d# 141 l

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3.6.(cont'd) JAFNPP 4.6 (cont'd) continued reactor operation is permissible for the succeeding-seven. days, unless such subsystem is

_ sooner made operable.

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'3. We Drywell Continuous Atmosphere 3. Drywell Continuous Atmosphc e Radioactivity Monitoring System shall Radioactivity Monitoring System be operable during reactor power opera- instrumentation shall be funct-4 ' tion. ionally tested and calibrated as specifed in Table 4.6-2.

a. The monitoring system shall be considered operable if at least one monitor is operable.

b. From and' after the tf the Dry-well Continuous' Atmosphere

, Radioactivity Monitoring System is made or found to be inoperable for any reason, continued reactor

, power operation is permissible provided:

1. We requirements of 3.6.D.2 are satisfied and 4

Amendment No.~ M 142

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I ATTACHMENT II SAFETY EVALUATION RELATED TO

. DRYWELL SUMP MO!!ITORING SYSTEM i

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POWER AUTHORITY OF THE STATE OF NEW YORK JAMES A. FITZPATRICK NUCLEAR POWER PLANT

. DOCKET NO. 50-333

APRIL 3 - , 1981 L..--_  %-_--- - - - - - - - --_m-xa x_ _ _ - _ -u---K_--__ - - _ . . . - - - - - - - - - - - - _ - - - - - - ------.m---a- -----a-h- -----_s-,,.---,a - - -- -. ------ -. - - -----u..a - - - - - - - -

Section I - Description of Modification The proposed change to the Technical Specifications is shown in Attachment I. The proposed changes occur in Section 3.6.D.2 and 4.6.D and clarify that RC leakage detection is accomplished by the Equipment and Floor Drain Sump Monitoring Systems. The proposed changes also clarify that it is these systems which must be operable, whereas the present Technical Specifications require redundant components be operable.

Section II - Purpose of Modification The purpose of the modification is to make the Specifications con-sistent with the Bases given on page 151 and to remove the present requirement that the reactor be shutdown 30 days after deter-mination that a redundant component of the pertinent subsystem is inoperable, unless the component is sooner made operable. The intent of the systems is to provide monitoring of the Reactor Ccolar.t leakage. Failure of a single component (Pump) either the equip-ment or floor drain systems does not result in loss of the monitoring and thus the 30 day requirement does rot serve any purpose. How-ever, the requirement for shutdown seven (7) days after determination that one of the pertinent subsystems is inoperable is retained.

Section III - Impact of the Change The proposed changes to the Technical Specifications do not change any system or subsystem. The present methods of ronitoring for RC system leakage is described in the NRC Safety Evaluation for Amendment 28 to the JAF Technical Specifications and will not be changed by implementation of the requested Tech. Spec. changes.

Section IV - Impicrentation of the Modification The modification as proposed will not impact the ALARA or Fire Protection Prngram at JAF.

Section V - Conclusion The incorporation of these modifications: a) will not change the probability nor the consequences of an accident or malfunction of equipment important to safety as previously evaluated in the Safety Analysis Report; b) will not increase the possibility for an accident or malfunction of a different type than any evaluated previously in the Safety Analysis Report; and c) will not reduce the margin of safety as defined in the basis for any Technical Specification, and d) does not constituto an unreviewed safety question.

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Section VI - References (a) JAF FSAR (b) JAF SER l

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