ML20196H336

Advises of Schedular Change for in-containment Portion of Thermocouple Sys (T/C Sys) Upgrade.Change Will Not Affect Final Installation Date of T/C or Reactor Inventory Tracking Sys

ML20196H336
Person / Time
Site:	Kewaunee
Issue date:	02/20/1985
From:	Hintz D WISCONSIN PUBLIC SERVICE CORP.
To:	Varga S Office of Nuclear Reactor Regulation
References
CON-NRC-85-24, RTR-NUREG-0737, RTR-NUREG-737, TASK-2.F.2, TASK-TM TAC-45143, NUDOCS 8803100189
Download: ML20196H336 (13)

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' h' 2 E 9 2 8 February 15, 1985 Director of Nuclear ~ Reactor Regulation,, E Attention: Mr. S. A. Yarga, Chief.

Operating Reactors Branch No. 1 Division of Licensing.

r U.S. Nuclear Regulatory Commi'ssion Washington, D.C.

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Ina equate Core Coolin;'g Instrumentation-N

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.'.' Riference: - 1. Let' tee t'o S. A. Yarga of the'NRC_ from C. W.'Giesler of WPSC

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c, Inadequate core coolin'g instrumentation is defined by NUREG-0737 as that instrumentation required to detect the approach to inadequate heat removal from the reactor core.

ICC. instrumentation consists of the Reactor Inventory sc.

Tracking System (RITS), the Subcooling Margin Monitor (SMM) and the Core Exit.

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Thermocouple System (T/C system). Descriptions of,these systems and schedules for, implementation ~were previously transmitted to you (Peference 1).

Reference 1 scheduled the T/C system upgrade for completion in 1986 with the in-containment portion to be completed during our 1985 outage.

The purpose of this letter is to advise you of a change to this schedule for the in. containment portion of the upgrade.

The schedule previously submitted for completion of the T/C upgrade to a i

qualified system was premised on the availability of qualified components.

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have recently been informed by our supplier (Westinghouse) that the thermocouple connector and its seal failed its qualification test. We will be unable, therefore, to upgrade the in containment portion of the system during the 1985 outage as we previously anticipated.

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Mr. 5. A. Varga February 15, 1985 Page 2 This is acceptable, however, because the presently installed system will remain functional during the qualification of the new connectors and will continue to moet our operational needs.. Additionally, we have a qualified SMM installed which is operational. Thus we exceed our original licensing requirements in this area. The implementation schedule for the RITS remains unchanged.

At this time Westinghouse is selecting an alternate connector manufacturer for qualification testing. The connectors will be subject to complete qualification testing which is currently sch'eduled for completion in sufficient time for installation during the 1986 refueling. outage.

To summarize, the in-containment portion of the T/C system cannot be upgraded during the 1985 refueling outage due to the lack of qualifitd components; however, this will not affect the final installation date of the T/C or RIT Systems.

Therefore, this schedular change is acceptable.

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. Ver truly yours,

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D. C. Hintz 0:

Manager - Nucl.ar Power

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CHECKLIST FOR INADEQUATE CORE COOLING INSTRUMENTATION D A T E _ _ _,,,,,,,,... _ _*.._ _.

PLANT.__._,,,..,,....,_,,__,........ ____ DOCKET _,_____..___

UTILITY _

CLAR1rICATION ITEMS - NUREG-0737 ITEM !!.r.2-2.3 1.

Design of new instrumentation should provide an unambiguous indication of ICC.

This may require new measurements or a synthtais of existing measurements which meet design criteria (Item 7).

___,___. Unambiguous indication of ICC?

Yer No

[V8ut TT4 L O&TE $

Reference (Type):____....

f s%mo; O F l C e/6VITTFL

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2.

The evaluation is to include reactor-water-level indication.

.___ Reactor-water-level (inventory) indication provided?

Yes' No 1

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Reference:

3.

Licensees and applicants are required to provide the

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necessary design analysis to support the proposed final instrumentation system for inadequate core cooling and to evaluate the scrits of various instruments to monitor water level and to monitor other parameters indicative of core-j cooling conditions.

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.__,_____ Acceptable design and accuracy analysis?

j Yer No neierence:

4.

The indicotton of ICC must be unambiruous in that it should q

have the following properties:

i a.

It must indicate the existence of ICC caused by various rhenomenn fi.e.

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_________High void fraction pumped flow

. _______ Stagnant boil off

b.... _____It must not indicate ICC because of the presence I

of an unrelated phenomenon.

Reference:

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i 5.

The indication must give advanced warning of the approach of 1C0.

_________ Advance warning indications i

Reference:

l 6.

The indication must cover the full range from normal l

operation to complete core uncovery.

For example, water-I level instrumentation *may be chosen to provide advanced 1

warning of two-phase level drop to the top of the core and l

could be supplemented by other indicators such as incore and core-exit thermocouples provided that the indicated i

i temperatures can be correlated to provide indication of the existence of ICC and to infer the extent of core uncovery.

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i Alternatively, full-range level instrumentation to the i

bottom of the core may be employed in conjunction with other diverse indicators auch as core-exit thermocouples to preclude misinterpretation due to any inherent deficiencies or inaccuracies in the measurement system selected.

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.........-......................... Range of level indication I

7.

All instrumentation in the final ICC system must be j

evaluated for conformance to Appendix 3 "Design and Qualification Criteria for Accident Monitoring

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Instrumentation," as clarified or modified br he provisions of items 8 and 9 that follow.

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........ 0valification complete?

Reference:

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8.

If a computer is provided to process liquid-level stenals j

for display, scismic qualification is not required for the-j computer und associated hardware beyond the isolator or i

input buffer at n locntion accessible for maintenunce-J 1

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following and accident. The single-failure criteria of ites

2. Appendix B. need not apply to the channel beyond the isolation device if it is designed to provide 99%

availability with respect to functional cnpability for liquid-level display.

The display and associated., hardware beyond the isolation device need not be Class 1E. but should be energized from a high-reliability power source which is battery backed.

The quality assurance provisions cited in Appendix B.

item 5 need not apply to this portion of the instrumentation s} stem.

_,99% availability of ecaputer system primary display?

.. __.. Battery-backed, high-reliability power source?

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Reference:

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1 9.

Incore thermocouples located at the core exit or at discrete axial levels of the ICC sonitoring system and which are part of the monitoring system should be evaluated for conformity with Attachment 1 "Design and Qualification Criteria for PWR Incore Thermocouples."

,_______ Thermocouples in conformance with Attachment !?

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Reference:

I 10.

The typer and locations of displays a,nd alaras should be deterair.ed by performing a human-f actors analysis taking into consideration:

..,___ a.

the use of this inforastion by an operator during both normal and abnormal plant conditions.

.......b.

integration into emergency procedures.

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integration into operator training.

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other alarms during emergency and need for

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Reference:

1 11.

Changes to Technical Specification required to address ICCI i

availability.

_________ Technical Speci fica t ion changes made?

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Reference:

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ICCI CHECKLIST SUBC00 LING MARGIN MONITOR:

1.

....___ Display of saturation margin in degrees E or psi Yes No on demand?

Reference:

2.

___,____. Continuous display of delta-T to saturation?

Yes No

Reference:

3.

_________ Recording of margin-to-saturation provided?

Yes No

Reference:

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4.

......... Environmentally qualified from sensors to displays Yee' No or isolation. devices per RG 1.89 and RG 1.100,

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based on design basis accident event?

,,__,____ Isolation devices accessible for maintenance during (e*

No operation?

,__,_____ Continue to read with required accuracy following Yes No safe-shutdown-earthquake.

Reference:

5.

.._,_____ Redundant divisions provided?

Yes No

_____. Independent Channels?

______ Independent Class lE power sources?

9

... __ Physically separated, including isolation devices, per RG 1.75?

....__At least one channel displayed on direct-indicating or recording device?

Qualified isolation of signals for other use?

References:

6.

....... _Alaras provided?

Yes No

Reference:

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___,_____ Located and properly identified in control room?

Yes No

Reference:

8.

___,_____Means of checking during operation (including Yes No sensors)'

Reference:

9.

_____,__,. Adequate service, test and calibration?

Yes No

____,____ Administrative control of access to setpoints, i

1 Yes No calibrations, test points, and removal from i

ser,vice?

Reference:

10.

____,____ Availability of and training with steam tables and Yes No alternate indicators for backup margin calculation?

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ICCI CHECKLIST l

CORE EXIT THERMOCOUPLES - PRIMARY DISPLAY 1.

..._,,__. Dis play a core asp on demand (both t rai ns-)?

Yes No Reference

• 2.

__,...___ Selective and continuous indication on demand?

Yes No

Reference:

3.

___..__ Show Highest temperature reading?

Yes No

Reference:

4.

____....-Show everage of five highest readings?

Yes No

Reference:

I 5.

___,___..Hard copy available on demand?

Yes No

Reference:

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6.

.__,,_____Lange of 200 to 1800 degrees F (or more)?

Yes No

Reference:

i 7.

___,_____ Trend capability?

Yes No

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Reference:

8.

___,_____Alera Capability?

(Procedure entry)

Yes No d

Reference i

9.

...,_____ Human Factors applied to the design?

Yes No 1

Reference:

i 10.

___...___ Electrically independent of backup display?

Yes No

Reference:

11.

.....__.. Physically separated per RG 1.75 (both trains Yes No and backup?

Reference:

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___...... owered fro high reliability, battery-backed S

12.

Yes No source:

Reference:

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13.

__.,__.. Environmentally and aeismically qualified per valid Yes No reference?

._____.._Yessel Connectors

________.0ther in-containment connectors

______.. cables

_____.... containment penetrations

....___.. cold Junction reference bcxes

________. train separation

References:

14.

.........At least 99% availability?

Yes No

Reference:

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o ICCI CHECKLIST 1

BACKUP DISPLAY CORE EXIT THERM 0 COUPLES 1.

___...... Hardware is Class 1E, Environmental & seismic Yes No qualification per R0 1.89?

_....___ vessel connectors.

......___other in-containment connectors

____..... cables i

.......__ containment penetrations

...____. cold junction reference boxes

__....___ train separation

__....... isolation devices available for on-line maintenance

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References:

2.

___,,,.__. Redundant, independent channels provided - meets Yes No single failure criterion?

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Reference:

3.

___.Can read sixteen TCs (four per quadrant) in less Yes No than six minutes?

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Reference:

4.

___...___Four qualified TC inputs per core quadrant?

Yes No l

l Keference:

5.

___,___. Adequate range (200 to 2300 degrees F)?

Yes No j

Reserence:

6.

___. ____ Energized from station Class IE power sources.

Yes No El,ectrically, independent of primary disolav*

References:

7.

_......... Signals isolated from primary display?

Yet No

Reference:

4 8.

....... Available prior to accident?

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Yes No l

Reference.

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9.

......___ Display accessible to the operator?

Ye; No aeference 10.

..._,____ Integrated into emergency procedures snd training?

Yes No

______ __ Basis for emergency procedures?

References:

11.

...._____ Physically separated from primary display per RG 1.75?

Reference:

12.

__....___ Availability addressed in Technical Specifications?

Yes No

Reference:

13.

___,_____ Service, test and calibration progras?

i Yes No j

_________ Administrative control of access to setpoints.

calibrations, test points, removal from service?

Reference:

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ICCI CHECKLIST REACTOR VESSEL LEVEL INSTRUMENTATION 1.

,__._____ Measurement range adequate?

yea No neference:

2.

___,_____ Measured variable and accuracy adequate?

Yes No (acceptance guideline +/-64)

Weference:

3.

___,._____Use of environmentally qualified components?

Yes No

____,____ Qualified dp cells with adequate accuracy under degraded environmental conditions? -or:

_________dp cells located outside containment?

_________ Density compensation provided for reactor vessel and dp sense lines?

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_________ Qualified Heated-Junction-Thermocouples

Reference:

4.

,__,,_____ Redundancy provided?

Yes No

Reference:

5.

___,_____ Instrumentation available at all times?

Yes No neference:

6.

,__,_____ Interfaces to non-lE equipment is through qualified I

Yes No and accessible isolation devices?

Heference:

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7.

___,_____ Maintenance, testing and calibration programs Yes No adequate?

Reference:

B.

_________ Human factors considered in design?

Yes No I

Reference:

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