ML20067E587

Provides Addl Specific Details on RCS Level & RCS Temp Instrumentation as Requested as Result of Recent Site Insp of Activities Associated W/Generic Ltr 88-17 Re Programmed Enhancement 1 - Instrumentation

ML20067E587
Person / Time
Site:	Beaver Valley
Issue date:	02/06/1991
From:	Sieber J DUQUESNE LIGHT CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
GL-88-17, NUDOCS 9102150168
Download: ML20067E587 (11)

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byer WHeyivwer Statior 5twangport. PA 15077-0004 OSdExec" February 6, 1991 O

U._S.--Nuclear Regulatory Commission Attn:

Document Control Desk

! Washington, DC 20555

Reference:

Beaver Valley Power Station, Unit No. 1 and No. 2 BV-1 Docket No. 50-334, License No. DPR J BV-2 Docket No. 50-412, License No. NPF-73

Subject:

Supplemental Response to Generic Letter 88-17, Program Enhancements

.The purpose. of this letter ~ is to provide additional. specific details on RCS level..and RCS temperature instrumentation as requested' by NRC staff reviewers as a result of a:recent site' inspection of activities

' associated 'with Generic Letter 17._

Supplemental information.to Programmed Enhancement. No. - -1 HInstrumentation" is

[

-provided in Enclosure I'of this correspondence.

In-addition-to the above,_we have experienced difficulty in

-meet 1ng the implementation schedule of Generic Letter 88-17; Loss of.

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Decay Heat Removal.

Our--letters.-dated.. February 23, 1989 and March 19,,.1989, provided a response to the Generic Letter programmed enhancements..

The schedule: requested.by the NRC was to complete programmed' -enhancements consisting' of hardware installation and/or-modification by'_ the~ end of the second refuelingtoutage'following-Lreceipt of-~the Generic-Letter..'By. letter dated December-26, 1990,we advised ~the-NRC-that the_implementationiof modifications on Unit No.

2 would

.be. delayed until'the third refueling outage unless a need to.

'1

-enter. a. reduced inventory condition occurred earlier..

In that case, J

.we,would-complete the modifications-at that time.

Our_

original Unit-No. -

1 programmed ' enhancement commitments.

I include' c'ompleting _ modifications _by the end.-of the eighth refueling

. outage' scheduled.to _'begin' April 12,-1991.. We will not be able to meet that schedule due.to encountering the following difficulties and l delays throughout the course-of design detail development.

We still lack complete engineering details for the vendor supplied-ultrasonic instru.nentation.

(ref:

December 26, 1990, submittal).

The support details for upgrading the RCS level transmitter 4

instrumentation tubing from _ temporary to permanent'are not ready-- for issue to the field for fabrication.'(We will obtain field measurements during the eighth refueling outage I

0 to allow development.'of the installation details).

03 91021501 150014 P" " '68 910206"SF 1

Supplemental Response to Generic Letter 88-17, i

Program Enhancements

~Page,2 We will continue to work on these modifications to assure completion prior to need (i.e., operation at reduced inventory) or the end of the next refueling outage scheduled to begin December 10, 1992.

If you have any questions, please contact me or members of my staff.

Sincerely,

}&

D.

Sieber Vice President Nuclear Group cc:

Mr. J.

Beall, Sr. Resident Inspector Mr. T.

T.

Martin, NRC Region I Administrator Mr.

A.

W.

DeAgazio, Project Manager Mr.-R. Saunders (VEPCO) l l

4 '

Braver Valley. Power. Station, Unit No. 1 and No. 2 BV-1 Docket No. 50-334, Licensc No. DPR-66 BV-2. Docket No. 50-412, License No. NPF-73

, Supplemental Response to Generic Letter 88-17, Program Enhancements Page 2 i

boc:

ORC Members L

OSC Members K.D.

Grada T.P. Noonan W.S.

Lacey D.E.

Spoerry F.D.

Schuster J.V. Vassello G.S. Sovick J.E.

Matsko F.S.

Pajak J.

Forney L.R.

Jreeland F.J.

Schaffner R.E.. Martin T.W.

Burns R.W. Fedin Central File (2)

Licensing File

+1

]

ENCLOSURE'I SUPPLEMENTAL RESPONSE TO GENERIC-LETTER 88-17 c.1

" PROGRAMMED / ENHANCEMENT NO. 1 - INSTRUMENTATION" Instrumentation'Recuirements Der-Generic' Letter 88-17

-Provide-reliable' indication of parameters that describe the-state of the RCS 'andithe_ performance-of systems normally used to cool the RCS for' -both~ normal and accident conditions.

At a minimum, provide the following.inithe. control Room:

(a) TwoLindependent RCS_ level indications.

.(b) At.least; two independent temperature measurements representative _

l of the core exit whenever the RV head is located on top of the RV L(We suggest that temperature indications be provided at all; E

' times).

I (c)iThe capability-offcontinuously monitoring DHR system performance whenever a:DHR system is being used for cooling the RCS.

1 (d).cVisible- _ _and.

audible. indications lof -abnormal-conditions in temperature, level,1and DHR_ system performance.

I

.Sunolemental Information t BVPS Unit'1

' Level Indication (BVPS Unit 1):

Reliable' indication of-RCS level 1during operation at a reduced

-reactorL

'olant. system inventory--is currently provided by_two (2)

. temporary _ _ level'_ transmitters'and. temporary tubing-on the "A" and.

"C"' cloops.z ?The temporary _ equipment will be: permanently installed-

and,will1 provide two' independent: RCSLlevel indications to satisfy; Lthefguidelines"ofjthis Generic Letter ~.

In-a'ddition, an' ultrasonic level-transmittertwill-be added;to'the

~

-" A'F f hot. leg a s' supplemental,

-independent RCS' level indication 1during mid-loop operations.

This instrument may.be substituted' for-one-' 13 f the-above level' transmitters when in a reduced inventory condition..

These. instruments.willybe provided with' visual.-and audible indications of abnormal ' conditions in_the-Control"_ Room.

Table 1 IA-provides. specific details of 'the level instruments including type,- accuracies,

range, and-alarm capabilities.for

-Uniti 1'.

Table

-IB-identifiesL the tap _ connections, respective

-elevations-and locations for theLRCS level' instruments utilized 1during mid-loop _ operations.

Mid-loopL _ operation 'also requires the operations personnel to

-closely monitor various equipment parameters utilizing the-station logs (L5-45,-46:and 47).

Parameters monitored are:

RHR. pump flow and temperatures RHR_ pump amps RCS temperatures RCS level 1

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Enclosurcil,1 continued ND3NSM:4951E Pagel2; Anytime.tihe -level indications disagree by more than-5xinches or

'the' remote' -level' transmitters-are out of service, continuousi l

Jmonitoring-

?*

a local _ standpipe is. initiated and called into the; Control-Room every 15 minutes or immediately if significant_ rapid level ~ changes occur ( > 1 inch)..

Anytime RCS

level, RHR flow, or RHR pump amps are unstable, the following actions are~taken.

t Vent RHRzpumps once an hour.

1 Log-vent-time, RHR pump amps and core' thermocouple readings each' hour on-the Reactor Operator Log.

(Two' incore.

thermocouples per core quadrant).

Continue. hourly -venting-until there is no evidence of' air and the -local-standpipe and.the remote level transmitters agree withiiL5: inches-.

Temperature, Indication (BVPS Unit 1):

JCore exit thermocouples (CETCs) willLbe utilized to monitor the JRCS.during _mid-loop. operation.

The operating surveillance logs will71requiref the; operators tofrecord thermocouple readings twice per-shift.z The: need

.for - providing alarm. capability of-the

. thermocouple _, temperatures-has-been evaluated and-determined to be-

-unnecessary...

There is-sufficient monitoring of. RHR system:

performance-to provide an early warning of a potential lossJof core cooling.

The operator is' responsible for acknowledgingrand-Lresponding1 to all Control Room / alarms.

An alarm associated with the CETC's-could -become a deterrent.to the operators in lieu'of lthei.various.. alarm / annunciation.capabilitiescinithe Control: Room or3 Efor; detecting. the onset of any. abnormal conditions-or 3

inalfunctions.

. The 1 monitoring of; the. operating-Lparameters j

fdiscussed'

'previously Lin combination withe operator. awareness; l

Lthrough

. training __ provide assurances.that the loss-of RHR capability?is significantly reduced..

' IIL Suppl lemental Information ~'BVPS Unit a q

Level 1 Indication (BVPS Unit 2):

Reliable indication of.RCS -level during operation at a' reduced l

reactor coolant. system-inventory-is currently provided' - by a'

. permanently; installed' level'- transmitter [2RCS-LT102) on'the'"C" loop..

oThere also -exists a Magnicator level gage (site glass) whicht-is permanently : installed and: monitors the RCS between the-pressurizer and the'RCS piping centerline, i

In, order to satisfy the need_ for two independent level

-indications defined in the generic letter, an ultrasonic level-1 transmitter will be added to the "A" hot leg. 'The ultrasonic

level transmitter will monitor narrow range mid-loop level and have the' capability for Control Room indication and alarm.

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L'ncionuroLI,' continued

ND3NSM:49511 y

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Page; 3:

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n LTable IIA = provideia specific ' details of Lthe levelLinstruments i

~ including __ type, accuracies,.

range,- and; alarm capabiliti~es for-

~

Unit 1 2.

' Table ZIB: -identifies the tap connections, respective-elevations.'and ; location-for the RCS' level-instrumentsLutilized-

[

.during mid-loop operations.

E

'Mid-loop operation" also : requires.the operations ' personnel to; closely.

_. monitor-.

various-equipment., parameters utilizing the--

Station Logs (L5-51, 52 and 53).-

Parameters monitored are:_:

I RHR; pump _ flow-RHR pump amps 3

'RCS temperatures LRCS level 1

Wheni draining-the RCS while in a reduced inventory-condition,Lthe ~

change in : level is monitored by the level transmitter indicator-

-iniethe -Control Room and continuous sonitoring of the local ~ gauge-glass:,whose; readings' are called into the Control Room:.every 15 minutes.

1 Anytime LRCS level,-

RHR ' flow or RHR pump amps are unstable, the!

-following actions are taken:

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t i

Vent RHR pumps once an hour.

. Log. vent -time,:RHR pump. amps and core' thermocouple readings-

=

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each' ihour on the Reactor-Operator = Log.

(Two incore thermocouples per= core quadrant).

t Continue hourly ; venting until there is.norevidenceLofiairL within-i Slinches.

_ indicator agrees 1,

and -the. local-standpipe and remote level

^With the.one.

(1).'

wide jrange ; remote level transmitter and'the:

1 addition ~<-of:

the.

ultrasonic.: level transmitter,. we believe adequate,. rel-iable, _and independent' RCS

. level indication is-

.provided1for. satisfying-Generic Letter 88-17.

l

-Temperature / Indication (BVPS Unit 2):

-q Core Lexit thermocouples

-(CETCs) will be: utilized in a manner 1similar to Unit 1 to monitor ~the RCS during mid-loopLoperation.<

1The Loperating surveillance logs will require the' operators to-record thermocouple readings twice per _ shift.

The needffor.

j providing_ alarm capability.

of_tha thermocouple temperatures'has.

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been'? evaluated and determined to be ~ unnecessary.

There'is

'sefficientL monitoring of RHR' system performance to' provide an:

early " warning of-a potential loss of core. cooling.

The' operator-1s!' responsible for acknowledging and responding to all1 Control Room alarms.

An-alarm associated with the CETC's could become.a r

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t Enclonuro I, continued ND3NSM:4951 Page,4

-deterrent to-

-the operators-in lieu of the various

-alarm / annunciation capabilities in the Control. Room or for detecting the onset of any abnormal conditions or malfunctions.

• he monitoring of the operating parameters discussed previously in combination with operator awareness through training should provide assurances that the loss of RIIR capability is significantly reduced.

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TABIE YA - RCS IEvel Instrumentation,- BVPS Unit 1-Invel Instrumentation Type Rarne Accuracy Alarns BV-1 Rosemount 0-750"

.25% of.

Hi/Io Alarrs to C.R.

Two (2) Level Transmitters (Calibrated Full Range (SG level outputs)

(WR) over 0-200" Range)

(0-750")

Two-pen Recorder in Control Rocra

("A" Icop and "C" Loop)

Ultrasonic Invel Ultrasonic Probe 0-30" i 1" Will be alanned to C.R.

Transmitter (NR)

.(Hot leg I.D. = 29")

(XR 'IB. 202 to be. used for:

["A" Hot Ing"]

100-40% of full pipe monitoring and annuncia-(= 11.6" @ 40% level) tion).

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L REE IB-PIS Level Instncent Taps /Inmtion Invel Instnrent (B7-1)

Taps / location (Drairdowr0 Taos /locaticn (Mid-loco)

LT-TDiP-]A-3I RC *1C-216, 217 or 218-(hE)

("A" Ctiid Igg Vent)

Root stop valves (for ET-PC 415, 416, 417)

EL = 732'3 15/16" EL :: 726'6" (8700 - RP-8F Iso. trwg.)

(8700 - RP-8F Iso. Drwg.)

I F Ia4P-1C-3I RC-54

• RC-224 (h2)

("C" Cb1d Ieg vent)

(IT-RC-434 Isol. Valve)

EL = 732'3 15/16" E - 726'6" LT-RC-480 Hot Ing piping (UTuasenic transmitter)

(Centerline = EL 732' 3 15/16")

"A" Hot leg Pange 0-30" Piping ID = 29"

• trJIE hhen level gets down to mid-loop irdication, the tap connections for 1 of the 2 locps are d=uspd frun hR to a narrower range for reading lower levels and recalibrated for loop level inlication.

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U.BIE JYA - RCS Zevel Instrum.entaticn, BVF5 Uhit 1 level Instrurertation Type Rarne Accuracy Alan's BV-2 Rosenount 0-180"

.25% of fli/Io Alanns to C.R.

IRCS Invel Transmitters Rill Range (h&:r in C.P-)

car)

(0-180")

[2RG-LT-102]

U1Lascaic level Ulk dc Probe 0-30a i 1" Will be alarmed to C.R.

Transmitter (NR)

(Ibt Ieg I.D. = 29")

[ Existing lo:p 2 SIS-LI920

{2RC-LT-103]

100-40% of full pipe aryl recorder 2LMS-IR950

(:: 11.6" @ 40% level) to be used for CR l

inlication ard annunciation].

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. -... I -

e TABLE IIB-RCS Level Instrument Taps / Location s

Lovel Instrument ( DV-1J.

Taps / Location 2RCS-LT-102 2RCS-750-272-2 (WR) to 2RCS-750-273-4 EL = 730'8" (off Hot Leg "C" Piping)

(Drwg. # 280 6263920-817 and

1. 280 6258920-700G]

2RCS-LT-103 Hot Leg Piping (Ultrasonic Transmitter)

(Centerline - 732'3 15/36")

"A" Hot' Log Range 0-30" Piping ID-29" l

. _ _ _, -. _. ~ -. _ -

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