ML20154D458

Proposed Tech Specs 3/4.4.6 Re Reactor Coolant Sys Leakage Detection Sys

ML20154D458
Person / Time
Site:	Byron, Braidwood, 05000000
Issue date:	05/06/1988
From:	COMMONWEALTH EDISON CO.
To:
Shared Package
ML20154D441	List: ML20154D437 ML20154D458
References
NUDOCS 8805190202
Download: ML20154D458 (6)

Text

_. _ _ _ _ _ _ _ _ _ _ _ _ _ - - _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _.

I ATTACHMENT A PROPOSED CHANGE TO APPENDIX A TECHNICAL. SPECIFICATIONS, FACILITY OPERATING LICENSES NPP-37, HPF-66, NPP-70 and NPF-75 Revised Pages: Byron pgs. 3/4 4-20 3/4 4-20a Braidwood p. 3/4 4-20 l

r i

l l

8805190202 880506 PDR ADOCK 05000454 P

DCD

. l-L REACTOR COOLANT SYSTEM 3/4.4.6 REACTOR COOLANT SYSTEM LEAKAGE LEAKAGE DETECTION SYSTEMS QMITING CONDITION FOR OPERATION 3.4.6.1 The following Reactor Coolant System Leakage Detection Systems shall be OPERABLE:

a.

The Containment Atmosphere Particulate Radioactivity Monitoring System, b.

The Containmen_t_ Floor Drain and Reactor Cavity Flow Monitoring Syste and oc Swp Acc w Range. Level Instrumn+sj c.

The Con alnment Gaseous Nadioactivity Monitoring System.

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

ACTION:

a.

With a. or c. of the above required Leakage Detection Systems inoperable, bon Nf-operation may continue for up to 30 days provided grab samples of the

, [g) G4;gnp containment atmosphere are obtained and analyzed for gaseous and particulate radioactivity at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> when the required Gaseous or

, Floor Dram, and Particulate Radioactivity Monitoring System is inoperable; otherwise, be in b eter Cavity 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 />, Flow Monifering b5 the [?.) 1 ""bp 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 tb,

.h=of=tM= regs-ed Leh;e Demon = Systems inoperable be in at Ngerow Ran3e foll wing 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

d Instru e I With a. and c. of the above required Leakage Detection Systems inoperable:

1)

Restore either Monitoring System (a. or c.) to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> and 2)

Obtain and analyze a grab sample of the containment atmosphere for gaseous and particulate radioactivity at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, and 3)

Perform a Reactor Coolant System water inventory balance at least once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-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 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />, i

SURVEILLANCE REQUIREMENTS 4.4.6.1 The Leakage Detection Systems shall be demonstrated OPERABLE by:

a.

Containment Atmosphere Gaseous and Particulate Monitoring System-performance of CHANNEL CHECK, CHANNEL CAllBRATION, and DIGITAL CHANNEL OPERATIONAL TEST at the frequencies specified in Table 4.3-3, BYRON - UNITS 1 & 2 3/4 4-20 AMENDMENT NO.12 L

i

REACTOR COOLANT SYSTEM 3/4.4.6 REACTOR COOLANT SYSTEM LEAKAGE ITAKAGE DElECTION SYSlEMS SURVEILLANCE REQUIREMENTS (Continued) b.

Containment Floor Drain and Reactor Cavity Flow Monitoring System-performance of CHANNEL CAllBRATION at least once per 18 months,# tat l

c.

Verify the oil separator portion of the containment. floor drain collection sump has been filled to the level of the overflow to the containment floor drain unidentified leakage collection weir box once per 18 months, following refueling, and prior to initial startup, and l

d.

Veri [7 nvenfory per i

6 eci ficafion 4. 4. 6. 2. I b u sin 3 + be.

7 Suur Narrew Range. Lev e.I Tas /ruments at least once.

l per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

i i

1. The specified 18 month interval may be extended to 32 months for Cycle 1 only.

BYRON - UNITS 1 & 2 3/4 4-20a AMENDMENT NO.

s REACTOR COOLANT SYSTEM 3/4.4.6 REACTOR COOLANT SYSTEM LEAKAGE h

LEAKAGE DETECTION SYSTEMS ~

LIMITING CONDITION FOR OPERATION 3.4.6.1 The following Reactor Coolant System Leakage Detection Systems shall be OPERABLE:

The Containment Atmosphere Particulate Radioactivity Monitoring System, a.

b.

The Containment Floor Orain and Reactor Cavity Flow Monitoring Syste g nd doc Sep Narros bn3e. Level Irisf rusents]

The Containment Gaseous Radioactivity Monitoring Sys*.em.

c.

APPLICAB g :

MODES 1, 2, 3, and 4.

ACTION:

With a. or c. of the above required Leakage Detection Systems inoperable, a.

bod ne.

operation may continue for up to 30 days provided grab samples of the

0) Conbient c ntainment atmosphere are obtained and analyzed for gaseous and particulate Roor brain ard radioactivity at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> when the required Gaseous or Particulate Radioactivity Monitoring System is inoperable; otherwise, be in Ruelor Cavify 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 SHUT 00WN within Flow tiestorin3 the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

5 55:*d 7

With 4:=ef=th= 2'overeequired= Leakage =Ge4ection=Systemt inoperable be in at W. (2) Swp leastHOTSTANDBYwithinthenext6hoursandinCOLDSHUTDOWNwitfiinthe go hge following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

Leve.1 c.

With a. and c. of the above required Leakage Detection Systems inoperable:

nstrustnh 1)

Restore either Monitoring System (a. or c.) to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> and 2)

Obtain and analyze a grab sample of the containment atmosphere for gaseous and particulate radioactivity at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, and 3)

Perform a Reactor Coolant System water inventory balance at least once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-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 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

SURVEILLANCE REQUIREMENTS 4.4.6.1 The Leakage Detection Systems shall be demonstrated OPERABLE by:

Containment At.nosphere Gaseous and Particulate Monitoring System-a.

performance of CHANNEL CHECK, CHANNEL CALIBRATION, and DIGITAL CHANNEL OPERATIONAL TEST at the frequencies specified in Table 4.3-3, b.

Containment Floor Drain and Reactor Cavity Flow Monitoring System-performance of CHANNEL CALIBRATION at least once per 18 months,# ant, l

Verify the oil separator portion of the containment floor drain c.

collection sump has been filled to the level of the overflow to the containment floor drain unidentified leakage collection weir box once per 18 months, following refueling, and prior to initial startup3 and p

1. The specified 18 month interval may be extended to 32 months for cycle 1 only.

BRAIDWOOD - UNITS 1 & 2 3/4 4-20 AMENDMENT NO.

d. hfy.ranbry pr Sm m dion M c.2.lb miij +b. 5-r Arrow Rvs' Level Indramnts at lus + once per 12 hourn.

n

'e e

ATTACHMENT B BACKGROUND INFORMATION The three reactor coolant system leakage detection systems in Technical Specification 3.4.6.1 are provided to monitor and detect leakage from the reactor coolant pressure boundary. These systems are consistent with the recommendations of NRC Regulatory Guide 1.45.

The current Byron Technical Specification allows a unit to continue to operate for up to 30 days when either the containment atmosphere particulate or gaseous radioactivity monitoring system is inoperable, provided grab samples are taken every 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. However, if the containment floor drain and reactor cavity flow monitoring system becomes inoperable, the unit must be shutdown. This requirement to shutdown a unit when two of the three redundant leakage detection systems are still operable is overly restrictive.

This proposed amendment would add the existing containment floor drain sump narrow range level instruments to limiting condition for operation 3.4.6.lb.

In addition, a new surveillance requirement would be added (4.4.6.1d) to verify sump inventory every 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> using the sump narrow range level instruments. This proposed technical specification will permit reactor operation to continue if the two containment atmosphere radioactivity monitoring systems are operable and either the containment floor drain and reactor cavity flow monitoring system, or the sump narrow range level instruments are operable. Alternate and diverse methods of monitoring reactor coolant system leakage will continue to be available with this proposed technical specification.

a i

i I

4

". s ATTACHMENT C EVALUATION OF SIGNIFICANT HAZARDS CONSIDERATION Commonwealth Edison has evaluated this proposed amendment and determined that it involves no significant hazards consideration. According to 10 CFR 50.92(c), a proposed amendment to an operating license involves no significant hazards consideration if operation of the facility in accordance with the amendment would not:

(1)

Involve a significant increase in the probability or consequences of an accident previously evaluated; or (2)

Create the possibility of a new or different kind of accident from any accident previously evaluated; or (3)

Involve a significant reduction in a margin of safety.

The proposed amendment would add the installed containment floor drain sump narrow range level instruments to the technical specification for leakage detection systems. Sufficient leakage detection capability will still exist under the provisions of the proposed technical specification to allow operators to detect and monitor any reactor coolant system (RC3) pressure boundary leakage and take action to prevent further degradation of the RCS pressure boundary. As a result, the probability of previously evaluated accidents will not be significantly increased by a revision to the technical specification for leakage detection systems.

The consequences of previously evaluated accidents are not affected by the availability of the RCS leakage detection systems because the RCS leakage detection systems do not function to mitigate the consequences of previously evaluated accidents. Their purpose is only to monitor and detect leakage from the RCS pressure boundary.

This proposed amendment only affects the availability of redundant and diverse RCS leakage detection systems.

It does not allow any new modes of operation beyond those normally performed at operating PWR's.

Additionally, this amendment does not allow any modifications to the plant.

l For these reasons, this proposed amendment does not create the possibility l

of a new or different kind of accident from any accident previously l

evaluated.

l The leakage detection systems in the technical specifications are l

designed to detect a one gpm leak in one hour. According to a Westinghouse leak-before-break study performed for Byron /Braidwood, the calculated leak rate through the postulated critical crack size in the primary loop piping l

l is at least 10 times greater than the sensitivity of those leakage detection systems. This margin is not affected by the proposed amendment.

For the reasons stated above, Commonwealth Edison believes this proposed amendment involves no significant hazards consideration.

4553K

.