ML20065L905

Proposed Tech Spec Change Request 195 Re Surveillance Intervals

ML20065L905
Person / Time
Site:	Oyster Creek
Issue date:	11/19/1990
From:	GENERAL PUBLIC UTILITIES CORP.
To:
Shared Package
ML20065L897	List: ML20065L895 ML20065L898 ML20065L905
References
NUDOCS 9012100158
Download: ML20065L905 (6)

Text

.. _. _

_.m_.__.._._.

...___.m_.__.

_.m m

T OYSTER CREEK NUCLEAR GENERATING STATION PROVISIONAL OPERATING LICENSE NO DPR-16 DOCKET No. 50-219 TECHNICAL SPECIFICATION CHANGE REQUEST No. 195 I

Applicant hereby requests the Commission to change Appendix A to the above captioned license as indicated below.

1.

Section to be Chanced The bases of Section 3.1, and Table 4.1.1.

i 2.

Extent of Chance a.

Section 3.1 Bases delete the phrase " initiate reactor isolation" l

from the description of the High Drywell Pressure Trip System.

t b.

Table 4.1.1; Items 1,3,4 and Sb change the surveillance frequencies due to the replacement of digital switches with analog transmitter and electronic circuitry.

c.

Table 4.1.1 Item Sa.

Change test frequency to.once per 3 months and correct remark to state "By. varying level in the sensor column".

d.

Table 4.1.1 Item 27a change remarks to " Calibrate by varying level in the eensor column" and reword the test interval from "every 3 months" to 1/3 months" for consistency.

3.

Chance Recuested Roplace the old pages 3.1-4, 4.1-5, and 4.1-8.

4.

Discussion Refer.to No SignLficant Hasards Analysis which immediately follows.

+

b i 210Q j E,Mo r.O. I J J 1 PDh-T P

,q ng'L K 05000 y7 FDe

.c.-.

OYSTER CREEK NUCLEAR GENERATING STATION PROVIS90NAL OPERATING LICENSE NO. DPR-16 DOCKET NO. 50-219 TECHNICAL SPECIFICATION CHANGE REQUEST No. 195 Thic Technical Specification Change Request has been determined to contain No Significant Hazards ao required by 10CFR50.91.

These evaluations are specified in 10CFR50.92.

I.

The first change 10 a correction to the bases of Technical Specification 3.1.

An error was identified in the description of the control functions for the High Drywell Pressure trip system.

The High Drywell Pressure Trip oystem does not initiate a reactor isolation function.

Therefore, these l

words are being removed to correct the error. As the bases of the technical specifications are not part of the technical specifications, no significant hazard can exist in thie error correction.

1 The ^econd requested change is to Table 4.1.1, Items 1 - High Reactor Presouro, 3 - Low Reactor Wat;,r Level, and 4 - Low-Low Reactor Water Level are being changed to reflect modifications performed over the last two refueling cycles as part of the Reactor Protection System upgrade project.

Digital switches were removed and analog instruments were installed for greater accuracy and drift characteristico.

A daily channe; check, which is already being performed, will be required on these instrumenta.

A test program by the analog transmitter vendor demonstrated that drift on the transmitters in these instrumento remaAned within 0.20% of the Upper Range Limit during a period of 30 months.

Table 4.1.1 Item Sb - High Water Level in the Scram DischA-Volume - Analog m

Scram in being changed to reflect modificatione performed during the 1983-1984 refueling outage to comply with ATWS requirements for instrumentation. Over 6 years of data on these instruments was available for revicw.

An engineering calculation was performed to determine the curveillance interni with respect to maintaining drift within acceptable limito.

It was determined that a tranomitter calibration by application of test pressure of once por 12 months was acceptable to onouro con,inued detector operability.

This requirement was placed in a new " Note 3".

(The previous Note 3 expired in 1986 and le being replaced). Additionally, Note 3 requir64 a calibration of the electronic proconsing circuitry and output biotables once per 3 months by injection of an electronic test current.

This quarterly test further ensures instrument operability.

Finally, a monthly single point test of the functionality of the output bistable verifies that the control function will operate if called upon.

Table 4.1.1 Item 27a - Scram Discharge Volume, Water Lovel High, Analog Rod Block la being changed as a result of the engineering calculation of the surveillance test resuits documented since the installation of the modification during the 1983-1984 refueling outage to comply with ATWS requirements.

The calculation has determined that the instrument p<rformance does not exhibit excessive drift and that the existing calibration frequency of once each refueling cycle is acceptable. The change being requested is in the Remarks section to limit varying the level in the sensor column to the calibration test, only. The electronic circuitry will be tested once per three months by injection of an electronic test signal.

As the electronic j

circuitry cannot distinguish between a signal from the detector and a signal from a test source, no significant change in test requiremento results.

III.' Table 4.1.1 Item 5a - High Water Level in the Scram Discharga Volume, Digital Scram is requested to be changed to allow instrument testing to be done once per 3 months.

Th-instrument has an existing calibration by varying level in the sensor column of once per three months. An engineering calculation was performed and determined that a test interval of once per 3 months which coincided with the calibration requirement was acceptable to ensure operation

)

witnin acceptable drif :. limits.

Additionally, the overall effect of the request for surveillance interval changes in Items Sa, 5b, and 27a (SDV instrumentation) would be to reduce the man-rem for these surveillances by approximately 60% to 80%.

These SDV surveillances presently require the greatest radiation burden on the instrument and control technicians. This reduction in unnecessary exposure is included in the Oyster Creek REM Reduction Program.

}

Therefore, the requested change has been analyzed to contain No Significant Hazard in that it does not:

1.

Involve a significant increase in the probability or consequences of an accident previously analyzed.

As the requested change has been analyzed to ensure that acceptable drift limits are not exceeded and utilize existing installed hardware, no increase in the probability or consequences of a prev'ously analyzed accident is possible.

2.

Create the possibility of a new or different kind of accident from any accident previously evaluated.

As the requested ch.nges are only schedular and involve no changes to any installed system, no new or different type of accident than any previously analyzed is possible, 3.

Involve a significant reduction in the margin of safety.

As the requested changes are schedular and no not involve any setpoint changes, and the schoduler changes have been determined to meet acceptable drift '.imite no reduction in the margin of safety is possible, i

l 1

i

.~

particular protection instrumsnt is not required; or the plant is placed in the protection or safe condition that the instrument initiates. This is accomplished in a normal manner without subjecting the plant to abnormal operations conditions.

The action and out-of-service requirements apply to all instrumentation within a

_particular function, e.g.,

if the requirements on any one of the ten scram functions cannot be met then control rods shall be inserted.

The. trip level settings not specified in Specification 2.3 have been included in this specification.

The bases for these settings are discussed below.

The high drywell pressure trip setting is S 3.5 peig.

This trip will scram the reactor, initiate containment spray in conjunction with low low reactor water l

level, initiate core spray, intutate primary containment isolation, initiate automatic depressurization in conjunction with low-low-low-reactor water level, initiate the standby gas treatment s/ stem and isolate the reactor building.

The scram function shuts the core down during the loss-of-coolant accidents.

A steam leak of about 15 gpm and a liquid leak of about 35 gpm from the primary system will cause drywell pressure to reach the scram point; and, therefore, the scram provides protection for breake greater than the above.

High drywell pressure provides a second means of initiating the core spray to mitigate the consequences of loss-of-coolant accident.

Its trip setting of $3.5 peig initiates the core spray in time to provide adequate core cooling.

The break size coverage of high drywell pressure was discussed above. Low-low water level and high drywell pressure in addition to initiating core spray also causes isolation valve closure.

These settings are adequate to cause isolatior, to minimize the offsite dose within required limits.

It is permissible to make the drywell pressure instrument channeAu inoperable during performance of the integrated primary containment leakage rate test provided the reactor is in the cold shutdown condition. The reason for this is that the Engineered Safety Features, which are effective in case of a LOCA under these conditions, will still be r Nective because they will be activated (when the Engineered safety Features system is required as identified in the technical specification _of the system) by low-low reactor water level.*

The scram discharge volume has two separate instrument volumes utilized do detect water accumulation.

The high water level is based on the design that the water in the SDIV's, as detected by either set of level instruments, shall not be allowec to sxceed 29.0 gallons; thereby, permitting 137 control rode to scram.

To provide further margin, an accumulation of not more than 14.0 gallons of water, as detected by either instrument volume, will result in a rod block and an alarm.

The accumulation of not more than 7.0 gallons of water, as detected in either instrument volume will result-in an alarm.

Detailed analyses of trannients have shown that sufficient protection is provided by other scrams below 45% power to permit bypassing of the turbine trip and generator load rejection scrams. However, for operational convenience, 40% of rated power has been chosen as the setpoint below which these trips are bypassed.

This setpoint is coincident with bypass valve capacity.

A low condenser vacuum scram trip of 23 inches Hg has been provided to protect the main condenser in the event that vacuum is lost.

A loss of condenser vacuum would cause the turbine stop valves to close, resulting in a turbine trip oyster Creek 3.1-4 Amendment No: 20, 73, 79, 112

• Correction:

11/30/87

TABLE 4.1.1 O

CALIBRATION AND TEST FREOUENCY FOR PROTECTIVE INSTRUMENTATION A

MINIMUM CHECK, m

n Instrucent channel Check Calibrate Test Remarks (Applies to Test and Calibration _l x

xm x

1.

High Peactor Pressure 1/d Note 3 1/Mo m

2.

High Drywell Pressure (Scram)

N/A 1/3 mo.

Note 1 By appIication of test pressure 3.

Low Reactor Water Level 1/d Note 3 1/Mo 4.

Low-Low Water Level 1/d Note 3 1/Mo 5.

High Water Level in Scram Discharge volume a.

Digital N/A 1/3 mo.

1/3 mo.

By varying level in sensor columns b.

Analog N/A Note 3 1 mo.

6.

Low-Low-Low Water Level N/A 1/3 mo.

Note 1 By application of test pressure "s

t, 7.

High Flow in Main Steamline 1/d 1/3 mo.

Note 1 By application of test pressure 8.

Low Pressure in Main Steamline N/A 1/3 mo.

Note 1 By application of test pressure 9.

High Drywell Pressure 1/d Note 1 By application of cest pressure (Core Cooling) 10.

Main Steam Isolation Valve (Scram) N/A N/A 1/3 mo.

By exercising valve.

O>

33 mo oa thereafter according to Figure 4.1.1, with an interval not less than one month not more j

o NOTE 1:

Initially once/ month, I

y three months.

the reactor neutron flux peaking factor shall be estimated and

to

,5 NOTE 2:

At least daily during reactor power operation, if necessary, as specified in Section 2.3 t

flow-referenced APRM scram and rod block settings shall be adjusted, e

Specifications (1) (a) and (2)

(a,.

m Calibrate Calibrate electronic bistable trips by injection of an external test current once per 3 months.

NOTE 3:

transmitters by application of test pressure once per 12 months.

O TABLE 4.1.1

'(cont'd) 9 o

Instrument Channel check' Calibrate Test Remarks (Applies to Test and Calibration) b

27. Scram Discharge Volume (Rod Block) a) Water level N/A Each re-1/3 Mo Calibrate by varying level in high fueling-sensor column outage i

b) Scram Trip N/A" N/A Each re-bypass fueling outage

28. Loss of Power a) 4.16 KV Daily 1/24 mos.

1/mo.

Emergency Bus Undervoltage

.u (Loss of voltage) tm b) 4.16 KV Daily 1/24 mos.

1/mo.

Emergency Bus Undervoltage (Degraded Voltage)

29. Drywell High N/A Each re-Each re-O Radiation fueling fueling

roe outage outage an a (L oD g

• Calibrate prior to startup and normal shutdown and thereafter check 1/s and test 1/wk until no longer required.

- rt 4 g Leoend: N/A = Not Applicable;.1/s = Once per shift; 1/d = Once per day; 1/3d = Once per three days; 1/wk = Once perweek; 1/3 mo = Once every 3 months; 1/18 mos. = Once every 18 months m

The following notes are only for Item'15 of Table 4.1.1:

g A channel may be taken out'of service for the purpose of a check, calibration, test or maintenance without declaring the channel to be inoperable.

so,o a.

The channel functional test shall also demonstrate that control room alarm annunciation occurs if any of the following conditions exists:

g g

1) Instrument indicates measured levels above the alarm setpoint.

2) Instrument indicates a downscale failure.

g

3) Instrument controls not set in operate mode.

4) Instrument electrical power loss.

w

--- --