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Proposed Tech Specs,Revising RCS Leakage Spec 3.4.6.1 & Channel Calibr Surveillance Frequency for Containment Particulate & Gaseous Radiation Monitors
	ML20246B806
Person / Time
Site:	Beaver Valley
Issue date:	08/14/1989
From:	; DUQUESNE LIGHT CO.
To:	;
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ML20246B799	List: ML20246B796; ML20246B802; ML20246B806;
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	NUDOCS 8908240025
	Download: ML20246B806 (11)
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ATTACHMENT A-1 i

Revise the Beaver Valley Power Station, Unit No. 1 L,

Technical Specification as follows:

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ItE'CTOR COOLANT-SYSTEM A

3/4.4.6 REACTOR COOLANT SYSTEM LEAKAGE LEAKAGE DETECTION SYSTEMS LIMITING 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 containment sump discharge flow measurement system or narrow range level instrument, and c.

Containment atmosphere gaseous radioactivity monitoring system.

APPLICABILITY:

MODES 1, 2,

3 and 4.

ACTION:

a.

With one of the above required radioactivity monitoring leakage detec,: ion syntems inoperable, operations may continue for up to 30 days provided:

1.

The other two above required leakage detection systems are OPERABLE, and 2.

Appropriate grab samples are obtained and analyzed at least once per 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months s:

otherwise, Lbe in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

b.

With both of the above required radioactivity monitoring leakage' detection systems inoperable, operations may continue for up to 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months provided:

1.

The containment sump discharge flow measurement system or narrow range level instrument is OPERABLE, and 2.

A Reactor Coolant System water inventory balance measurement (Specification 4.4.6.2.d) is performed within the next four hours:

otherwise, be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

BEAVER VALLEY - UNIT 1 3/4 4-11 PROPOSED WORDING

RfACTOR COOLANT SYSTEM LIMITING CONDITION FOR OPERATION (Continued) c.

With the containment sump discharge flow measurement system l

and narrow range level instrument inoperable, restore at least-one inoperable system to OPERABLE status within 7 days or be in at least HOT STANDBY within-the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

d.

The provisions of specificat:'.on 3.0.4 are not applicable in l

Modes 1, 2 and 3.

SURVEILLANCE REQUIREMENTS 4.4.6.1 The leakage detection systems shall be demonstrated OPERABLE by:

a.

Containment atmosphere particulate and gaseous monitoring system-performance of CHANNEL CHECK, CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST at the frequencies specified in Table 4.3-3.

b.

Containment sump discharge flow measureme CALIBRATION TEST at lea,nt system-performance of CHANNEL st once per 18 months.

c.

Logging the narrow range level indication every 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

1 l

l BEAVER VALLEY - UNIT 1 3/4 4-12 PROPOSED WORDING L_______-------.-

ATTACHMENT A-2 Revise the Beaver Valley Power Station, Unit No. 2

-Technical Specifications as follows:

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R'EACTOR COOLANT SYSTEM l

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3/4.4.6 REACTOR COOLANT SYSTEM LEAKAGE LEAKAGE DETECTION SYSTEMS tINITING CONDITION FOR OPERATION 3.4.6.1 The following Reector Coolant System Leakage Detection Systems shall be OPERABLE:

The containment atmosphere particulate radioactivity monitoring a.

system,

(

b.

The containment sump discharge flow measurement system or narrow range level instrument, and Containment atmosphere gaseous radioactivity monitoring system.

c.

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

ACTION:

With one of the above required radioactivity monitoring leakage a.

detection systems inoperable, operatinns may continue for up to 30 days provided:

(

1.

The other two above required leakage detection systems are

~

OPERABLE, and 2.

Appropriate grab samples are obtained and analyzed at least b,

once per 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months s:

( @ $100*pW{

otherwise, be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

g l

With the containment sump discharge flow measurement system and Oc.f.

narrow range level instrument inoperable, restore at least one inoperable system to OPERABLE status within 7 days or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the

(

following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

~

Cd./ The provisions of Specification 3.0.4 are not applicable in MODES 1 2, and 3.

SURVEILLANCE PEOUIREMENTS 4.4.6.1 The leakage detection systems shall be demonstrated OPERABLE by:

Containment atmosphere particulate and gaseous monitoring system-a.

performance of CHANNEL CHECK, CHANNEL CALIBRATION, and CHANNEL FUNCTIONAL TEST at the frequencies specified in Table 4.3-3,

(

1 BEAVER VALLEY - UNIT 2 3/4 4-17 krape se.)

Qord

. Insert - Specification 3.4.6.1

' ACTION:

,b.

With both of the above. required radioactivity monitoring

-leakage detection systems inoperable, operations may continue for up to.12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months provided:

1.

The containment sump discharge flow measurement system or narrow range level instrument is OPERABLE, and 2.

A Reactor Coolant System water' inventory' balance measurement (Specification 4.4.6.2.d) is performed within the next 4 hour4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months s:

otherwise, be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

I 1

S BEAVER VALLEY - UNIT 2 PROPOSED WORDING

ATTACHMENT B Proposed Technical Specification Change Unit No. 1 - Change No. 1A-161 (Rev. 1)

Unit No. 2 - Change No. 2A-21 (Rev. 1)

Safety Analysis Description of Amendment Recuest The proposed amendment would revise the Reactor Coolant System (RCS) leakage detection systems specification 3.4.6.1 for Beaver Valley Units No.

1 and No.

2.

This revision provides an action statement for operation with both the containment atmosphere particulate and gaseous radiation monitors inoperable.

As currently

written, with both radiation monitors inoperable, specification 3.4.6.1 would require the plant (per specification 3.0.3) to initiate a

shutdown within one hour and be in HOT STANDBY within the next six hours and COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

The proposed action statement would allow operation to continue for up to 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months prior to initiating a plant shutdown provided the containment sump discharge flow measurement or narrow range level instrument is operable and, within the next four

hours, a

RCS water-inventory balance measurement is performed.

This amendment would also revise the channel calibration surveillance frequency for the containment particulate and gaseous radiation monitors.

Table 4.3-3 would be revised to include a

footnote which would allow the channel calibration frequency for these monitors to be extended to the next refueling outage if the interval between outages is greater than 18 months.

Discussion Specification 3.4.6.1 requires three independent methods for detection of RCS boundary leakage to be operable.

This is in accordance with the recommendations of Regulatory Guide 1.45.

Action statements are provided for one inoperable containment radiation monitor (gaseous or particulate) and for the containment sump discharge flow measurement system and narrow range level instrument inoperable.

Both the containment particulate and gaseous radiation monitors share a

common piping system and pumping arrangement.

Because of this design configuration, both radiation monitors must be taken out of service to perform the required periodic calibration and/or maintenance on either radiation monitor.

With both monitors inoperable while in operational modes 1 thru 4, per specification 3.0.3, within one hour the plant must initiate a plant shutdown and be in HOT STANDBY within the next six hours and COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

The time required to perform a

complete calibration on these radiation monitors is greater than six hours.

The proposed change will add an action 1

. Att chm:nt B Proposed Technical Specification Change Unit No. 1 - Change No. 1A-161 (Rev. 1)

Unit NO. 2 - Change No. 2A-21 (Rev. 1)

Safety Analysis l

Page 2

]

statement to allow both monitors to be inoperable for a sufficient i

amount of time to perform required maintenance and recalibration

{

of an inoperable monitor.

To ensure the capability to detect RCS j

leakage during the time period when both radiation monitors hre J

inoperable, the proposed action statement requires that the containment sump instrumentation be operable and a

RCS water inventory balance measurement be performed.

The proposed amendment would also revise the channel calibration surveillance interval for the containment particulate and gaseous radiation monitors to allow this surveillance interval to be extended to the following refueling outage if the interval between outages is greater than 18 months.

During the NRC review of the initially proposed amendment request, the NRC expressed concern with performing the periodic calibration of these radiation monitors during plant operation.

When performing this calibration, both monitors would be taken out of service leaving only the containment sump instrumentation available for leak detection.

While it was agreed that the proposed additional action statement for both radiation monitors being inoperable was necessary for any potential maintenance and re-calibration on an inoperable

monitor, it was concluded that periodic calibration of these monitors should be performed during plant shutdowns.

To ensure that these monitors would be calibrated during outages, rather than entering the proposed action statement to complete the periodic calibration, the channel calibration interval has been revised to allow this surveillance interval to be extended to the refueling outages.

l

ATTACHMENT C No Significant Hazard Evaluation Proposed Technical Specification Change Unit No. 1 - Change No. 1A-161 (Rev. 1)

Unit No. 2 - Chance No. 2A-21 (Rev. 1)

Basis for Proposed No Significant Hazards Consideration Determination:

The Commission has provided standards for determining whether a

significant hazards consideration exists (10CFR50.92(c)).

A proposed amendment to an operating license for a

facility involves no significant hazards consideration if I

operation of the facility in accordance with the proposed amendment would not (1) involve a

significant increase in the probability or consequences of an accident previously evaluated:

(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 change does not involve a significant hazards consideration because:

1.

This change will not cause a

significant reduction in the capability to detect RCS boundary leakage.

The revised specification continues to require three diverse means of continuously monitoring for RCS leakage.

For the short period of time when both containment particulate and gaseous radiation monitors are inoperable the proposed action statement provides adequate measures to ensure the capability to detect RCS leakage.

Extending the calibration surveillance interval of these radiation monitors will not cause a

significant reduction in the reliability of these monitors.

significant increase in the consequences of any Therefore, no accident previously evaluated results from this change.

2.

This change would not create the possibility of a new or different kind of accident from any accident previously evaluated.

There would be no change to system configurations, plant equipment or analysis as a

result of this proposed amendment.

3.

This change would not involve a significant reduction in a margin of safety.

The proposed revised Technical Specification will continue to require the operability of sufficient instrumentation to detect RCS leakage in accordance with the recommendation of Regulatory Guide 1.45.

Based on the above consideration, it is proposed to characterize the change as involving no significant hazards considerations.

_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _

ML20246B806

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