ML20090C161

Forwards Nonproprietary Final Sys Design Description for Reactor Coolant Inventory Trending Sys,Per NUREG-0737,Item II.F.2 & Proprietary, Summary Info RCS Coolant Inventory Trending (Cit).... Rept Withheld (Ref 10CFR2.790)

ML20090C161
Person / Time
Site:	Crane
Issue date:	07/06/1984
From:	Hukill H GENERAL PUBLIC UTILITIES CORP.
To:	Stolz J Office of Nuclear Reactor Regulation
Shared Package
ML19269A366	List: ML20090C161
References
RTR-NUREG-0737, RTR-NUREG-737, TASK-2.F.2, TASK-TM 5211-84-273, NUDOCS 8407130190
Download: ML20090C161 (36)

Text

F i

GPU Nuclear Corporation Nuclear

=,omg:,eo Middletown, Pennsylvania 170$7 0191 717 944 7621 TELEX 84 2380 Writer's Oltect Olal Number:

July 6, 1984 5211-84-2173 Offfce of Nuclear Reactor Regulation Attn J. F. Stolz, Chief Operating Reactors Branch No. 4 Division of Licensing U.S. Nuclear Regulatory Commission Washington, D. C.

20555

Dear Sir:

Three Mllo Island Nuclear Station Unft 1 (TMI-1)

Operating License No. DPR-50 Docket No. 50 289 Inadequate Coro Cooling (NUREG-0737 !!.F.2)

By letter dated June 14, 1903, the NRC provided conceptual design approval of our proposed RCS Inventory Tronding System.

The NRC further identiffed several concerns and requested a schedule for providing the requested information. By Ictter dated January 31, 1984 GpVN provided partial responses to the requested items and provided an interim system design description. The final design description (Attachment 1) is submftted in fulfillmont of the first milestono conmitment discussed in our responso of March 10,1983 (Drawing wfIl be sent separately).

Responsen to the remainder of the requested Items will be submitted in July, 1904. ontitied "RCS Coolant Inventory Trending (ClT) with RC Pumps Operating", providos the method for developing votd fraction for various RCS pump configurations based on motor power.

This attachmont replacos Attachment 2 of our submf ttal on January 31, 1984 which used motor current.

Part of the information (as rnarked) in this submittal is considered arcprietary by Babcock A Wilcox Co. under the provision of 10CIR2.790 as sworn 'y J.11. Taylor, a

Manager, Lfconsing, and should be treated as such.

Mr. Taylor's affidavit was attached to the submittal for Rev. O of this report.

Revisfon 1 contains an additional propriotary section. Section 2.6 not facluded in Revision 0.

The pagos Exhibit A and D have been rovtsed to reflect the document revision.

EYO Y' Sp OPU Nuclear Corporation is a nubnidiary of the General Public Utilition Corporation p l

5211-84 2173 Mr. John F. Stolz entitled "!CC Instrumentation Schedule (RCITS)" revises the previous schedule provided in our response of March 10, 1982.

The new schedule does not change our comitment to install the RCITS by startup from i

the Cycle 6 refueling outage (which is postponed until at 1 cast August 1985).

However, as discussed in our response to Comissioner Gilinsky of November 23, 1983. GPUN plans to complete installation in the fourth quarter of 1984 assuming TMl-1 has not restarted by then. Revision of the scheduled dates is based on more realistic engineering and construction projectior.- and a finalization of the design.

Concerning the status of the RCITS, GPUN has completed both a tap in the DitR dropline and a tie-in to the RV head vent, and is currently installin additional portions of the system Insido the THI-1 Reactor Dutiding. g Sincerely.

lo t

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0. Ilukill Director, THI-1 IIDH/LWH/SH0/mle Attachments cci R. Conte J. Van Vlfet

r MTN.lenfr 1 t

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Final System Design Description i

i For l

Three Milo Island ifnit 1 L

i Reactor Coolant Inventory

[

Trending System 1

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SDD 662C i

(DIV. II) t Rev. I l

Page 1 1.0 DSSIGN DESCRIPTION 1.1

SUMMARY

The purpose of this modification is the addition of a Reactor i

l Coolant Inventory Tracking System (RCITS) to the Three Mile Island Nuclear Generating Station Unit 1.

The RCITS provides a means for the Control Room operator to moni-I tor the water inventory of the reactor coolant system (RC8).

The RCITS is operational when the reactor coolant pumps are on or i

off.

Displayed water inventory data with the pumps off is useful l

as confirmatory information to other instrumentation of con-ditions which may interrupt natural circulation leading to a i

potential Inadequate Core Cooling (ICC) event.

The following t

water inventory displays are available for the control room j

operator when the pumps are of f s i

a.

Not leg of primary loop ' A' level b.

Not leg of primar loop 'B' level c.

Reactor vessel

'1 level (above ritel) d.

Reactor vessel '2 ' level (above ruel) l Each of these displays is compensated for fluid density variations.

This j

compensation is required to correct the level indications for two conditions.

The first is density changes in the fluid in the i

reactor vessel and reactor coolant piping due to temperature and i

pressure variations within the RCS.

The second condition is den-sity changes in the level transmitter reference lega due to l

variations in the ambient reactor containment building tem-perature.

I t

The RCITS also provides a means for the control room operator to monitor the void content of the reactor coolant system when the pumps are running.

Displayed void fraction data provided by the RCITS will be useful as anticipatory information of conditions which may interrupt normal circulation.

Void fraction displays l

i are provided for each of the four Reactor Coolant Purps (RCP's).

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SDD 662C (DIV. II)

Rev. 1 Page 2

1.2 REFERENCES

1.2.1 Industry 1.2.1.1 IEEE Standard 323-1974 Qualifying Class 1E Equipment for Nuclear Power Generating Stations 1.2.1.2 IEEE Standard 344-1975 Recommended Practices for Seismic Qualification of Class 1E Equipment for Nuclear Power Generating Stations 1.2.1.3 IEEE Standard 383-1974 Type Test of Class 1E Electric Cables, Field Splices, and Connections for Nuclear Power Generating Stations 1.2.1.4 NRC Regulatory Guide 1.89 Qualification of Class 1E Rev. 0 Equipment for Nuclear Power Plants 1.2.1.5 NRC Regulatory Guide Seismic Qualification of 1.100, Rev. 1 Electric Equipment for Nuclear Power Plants 1.2.1.6 NUREG 0680 Sup. 3 TMI-1 Restart SER 1.2.1.7 NUREG 0700 Human Factors Design Criteria for Control Rooms 1.2.1.8 NUREG 0737 II.F.2 Inadequate Core Cooling 1.2.1.9 USNRC-7590-01 Order for Modification of of Dec. 10, 1982 License for TMI-1 to Accommodate Additional In-strumentation to Detect Inadequate Core Cooling.

1.2.1.10 ASME Section III Boiler and Pressure Vessel (latest approved edition) Code 1.2.2 GPU Nuclear 1.2.2.1 1000-PLN-7200.01, Rev. O GPUN Operational Quality Assurance Plan

I SDD 662C (DIV. II) l Rev. 1 Page 3 1.2.2.2 SP-5616 GAI Specification for Elec-trical Work at Three Mile Island Nuclear Station Unit 1 1.2.2.3 SP-9000-44-001, Rev. O Specification for Instrument and Control Equipment Instal-lation l

1.2.2.4 TDR 282, Rev. 2 TMI-1 Qualified Equipment Locations and Environments t

1.2.2.5 SDD 662C System Design Description No.

(DIV. I), Rev. 6 662C DIV.

I, Reactor Coolant Inventory Tracking System 1.2.2.6 SP-90003-201, Rev. 3 GPUN Specification for Piping and Fittings.

1.2.2.7 SP-1101-43-004 Conduit and Conduit Support Installation Criteria for TMI-1 1.2.2.8 SP-5544 GAI Specification for Plant Piping at ihree Mile Island Nuclear Station 1.2.2.9 SP-5661 GAI Specification for Field Fabrication and Erection of Piping at Three Mlle Island Nuclear Station Unit 1 1.2.2.10 6150-ADM-3272.01,Rev.0 Inservice Inspection Program Development and Implementation 1.2.3 Burns and Roe, Inc.

1.2.3.1 Drawing M0002, Rev. O Flow Diagram - Reactor Coolant Vents Reactor Coolant Inventory Tracking System 1.2.3.2 Drawing M0003, Rev. O Flow Diagram - Decay heat Removal Reactor Coolant Inven-tory Tracking System 1.2.3.3 Drawir.g E002, Rev. O TMI Unit 1 Control Room Panel PCL (RCITS)

SDD 662C (DIV. II) l Rev. 1 Page 4 1.2.3.4 Drawing E003, Rev. O Loop Diagram - Hot Leg of Primary Loop

'A' Level (RCITS) 1.2.3.5 Drawing E004, Rev. O Loop Diagram - Hot Leg ot Primary Loop

'B' Level (RCITS) 1.2.3.6 Drawing E005, Rev. O Loop Diagram - Reactor Vessel i

Loop

'A' Level Above Fuel (RCITS) 1.2.3.7 Drawing E006, Rev. O Loop Diagram - Reactor Vessel Loop

'B' Level Above Fuel (RCITS) 1.2.3.8 Drawing E007, Rev. O Loop Diagram - Reactor Vessel Level for RCS draindown 1.2.3.9 Drawing E012, Rev. 1 Block Diagram - Reactor Coolant Inventory Tracking System i

1.2.4 Gilbert Associates, Inc.

1.2.4.1 Drawing 202-095, Block Diagram - Reactor Sht. RK-1, Rev. IA-0 Coolant Inventory Tracking System 1.2.4.2 Drawing 202-095, Block Diagram - Reactor Sht. RK-2, Rev. IA-0 Coolant Inventory Tracking System 1.2.4.3 Drawing 202-095, Block Diagram - Reactor Sht. RK-3, Rev. IA-0 Coolant Inventory Tracking l

System 1.3 DETAILED SYSTEM DESCRIPTION l

1.3.1 Water Level Trending Subsystem The water level trending portion of the RCITS is shown on Burns and Roe drawings M0002, M0003, E002, E003, E004, E005, E006, E007 and E012, and Gilbert Associates drawings 202-095, sheets RK-1, RK-2 and RK-3.

Drawings M0002 and M0003 are flow diagrams which identify where instrumentation is connected to the reactor coolant system and the decay heat removal system.

Drawings E003, E004, E005, E006 and E007 are instrument loop diagrams which l

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l

SDD 662C i

(DIV. II)

Rev. 1 Page 5 identify the details of each instrument loop.

Drawings E012 and 202-095, sheets RK-1, RK-2 and RK-3 are block diagrams which identify the interconnections for the major electrical com-E ponents.

Ther,q are five level measurements that are part of the RCITS.,

y are l

classified "Important to Safety" and " Nuclear Safety Related."

Details of these level measurements are as follows:

l 1.3.1.1 Hot Leg Level Primary Loop A

[

. Differential pressure transmitter RC-LT-1033 is installed between an upper connection at the top of steam generator RC-H-1A's hot leg and a lower connection upstream of decay heat line isolation valve DH-V-1.

This instrument measures the water level from the bottom to the top of reactor coolant loop A hot leg piping.

r The upper connection for RC-LT-1033 is equipped with a condensate pot and provides a water column reference leg for the transmitter.

Resistance temperature detector RC-TE-1033 senses the temperature of the water in RC-LT-1033's reference leg to compensate for density changes.

The signal provides density correction for both RC-LT-1033 and RC-LT-1035, since both reference legs are routed together, and will be exposed to the same ambient temperature.

Thermocouple RC-TE-1054 senses reactor coolant system. core exit temperature which is used to compensate for density changes in the reactor vessel head and hot leg fluids.

Resistance tem-perature detector RC-TE-1052 provides a cold junction reference temperature for thermocouple RC-TE-1054.

RC-TE-1054 is mounted in the existing Incore Detector Instrumentation structure, detector well No.

7.

RC-TE-1052 is mounted in terminal box T-1118 on the secondary shield wall near the incore detector rack, Reactor Building elevation 346'-0".

RC-LT-1033 is mounted on existing instrument rack No. TR10A at elevation 281'-0 inside the Reactor Building.

RC-TE-1033 is pipe mounted on the reference leg outside the D-Ring.

Power and signal. conditioning for these instruments is provided by existing Signal Conditioning Cabinet A2 located in the Control Building, El.

338'-6".

The density compensated level output signal is displayed via the plant computer,

SDP 662C (DIV. II)

Rev. 1 Page 6 1.3.1.2 Hot Leg Level Primary Loop B f

Differential pressure transmitter RC-LT-1034 is installed between an upper connection at the top of steam generator RC-H-1B's hot leg and a lower ccnnection upstream of decay heat line isolation valve DH-V-1.

This instrument measures the water level from the bottom to the top of reactor coolant loop B hot leg piping.

The upper connection for RC-LT-1034 is equipped with a condensate i

pot and provides a water column reference leg for the transmitter.

Resistance temperature detector RC-TE-1034 senses the temperature of the water in RC-LT-1034 's reference leg to compensate for density changes.

This signal provides density correction for both RC-LT-1034 and RC-LT-1036, since both reference legs are routed together, and will be exposed to the same ambient temperature.

i Thermocouple RC-TE-1055 senses reactor coolant system core exit t

temperature and is used to compensate for density changes in the reactor vessel head and hot leg fluids.

Resistance temperature detector RC-TE-1053 provides a cold junction reference tem-perature for thermocouple RC-TE-1055.

RC-TE-1055 is mounted in the existing Incore Detector Instrumentation structure, detector well No. 18.

RC-TE-1053 is mounted in terminal box T-1119 on the secondary shield wall near the incore detector rack, Reactor Building elevation 3 46 '-0".

RC-LT-1034 is mounted on existing instrument rack No. TR11B at elevation 281'-0" inside the Reactor Building.

RC-TE-1034 is pipe mounted on the reference leg outside the D-Ring.

Power and signal conditioning for these instruments is provided by existing Signal Conditioning Cabinet B1 located in the Control Building, El. 32 2 '-0".

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i The density compensated level output signal is displayed via the plant computer, j

1.3.1.3 Reactor Vessel Level 1 Differential pressure transmitter RC-LT-1035 installed between an upper connection at the reactor vessel head vent valves and a l

lower connection upstream of valve DH-V-1.

This instrument measures the level from the bottom of the hot leg piping to the top of the vessel head.

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l 1

SDD 662C (DIV. II)

Rev. 1 Page 7 l

The upper connection for RC-LT-1035 is equipped with a condensate pot and provides a water column reference leg for the transmitter.

t Density compensation is accomplished by utilizing the signals i

from temperature sensors RC-TE-1033, RC-TE-1054 and RC-TE-1052 as described in paragraph 1.3.1.1.

l RC-LT-1035 is mounted on existing instrument rack No. TR10A at i

1 elevation 281 '-0" inside the Reactor Building.

Power and signal conditioning for these instruments is provided by existing Signal l

Conditioning Cabinet A2 located in the Control Building, El.

3 3 8 '-6 ".

1 The density compensated level output signal is displayed via the plant computer.

1.3.1.4 Reactor Vessel Level 2 Differential pressure transmitter RC-LT-1036 is installed between i

an upper connection at the reactor vessel head vent valves and a lower. connection upstream of valve DH-V-1.

This instrument pro-I j.

vides a redundant level measurement for the reactor vessel head.

l t'

l The upper connection for RC-LT-1036 is equipped with a condensate pot which provides a water column reference leg for the i

transmitter.

I Density compensation is accomplished by utilizing the signals from temperature sensors RC-TE-1034, RC-TE-1055 and RC-TE-1053 as described in paragraph 1.3.1.2.

i RC-LT-1036 is mounted on existing instrument rack No. TR11B at elevation 2 81 '-0" inside the Reactor Building.

Power and signal conditioning for these instruments is provided by existing Signal i

Conditioning Cabinet B1 located in the Control Building, El.

322'-0".

l The density compensated level output signal is displayed via the

[

plant computer.

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--.-.....--.,~...~--.%---.---er--,.--a+-

n SDD 662C (DIV. II)

Rev. 1 Page 8 1.3.2 Void Fraction Trending Subsystem The void fraction trending portion of the RCITS is shown by Gilbert Associates block diagram 202-095, sheet RK-3.

This drawing shows the RCP power monitor inputs to the plant computer.

Pump power signals from each of four RCP cower monitors are transmitted to the plant computer wnere enese signals are con-verted to void fractions'via an empirical algorithm utilizing RCP power, pump status and RCS cold leg temperature data.

The c

void fraction algorithm was developed to yield the desired rela-tionship between RCP power and RCS void fraction at the pump suc-tion.

Four isolated signal transmitters IT-1 are mounted in sections A, B,

C and D of the Reactor Coolant Pump Power Monitor Rack A.

For each RC pump the transmitter receives an input from an existing watt-transducer and provides a non-1E RC pump power signal to the plant computer.

Transmitter power and existing watt-transducers are also located in RCP Power Monitor Rack A which is located in the Control Building, elevation 322'-0".

The void fraction measurement subsystem is classified as "Important to Safety".

1.3.3 Single Failure Design The RCITS is designed so that a single active failure other than the plant computer will not prevent trend displays of the reactor coolant void fraction or water level for at least one hot leg

u SDD 662C (DIV. II)

Rev. 1 Page 9 level measurement, one reactor vessel head level measurement, and one void fraction measurement.

The lower connections for all the level transmitters are connected to a single tap on the decay heat drop line.

The design philosophy with regard to redundant channels 1

utilizing a common connection is to separate these lines as soon as possible.

This philosophy is applied to this modification.

1.3.4 Piping, Valves and Tubing Design Piping is nuclear class N-2, seismic category S-I up to and including the root valves f rom the primary pressure boundary.

The tubing and instrument valves are nuclear class N-2, seismic category S-I.

The piping conforms to the requirements of line specification GP 2500-4 of reference 1.2.2.6.

Double valve iso-lation is maintained.

Snubbers and/or thermal loops are used at the tie-in points.

Instrument tubing and valves conform to the requirements of reference 1.2.2.3.

1.3.5 Electrical Design Electrical components of the water level trending portion of the RCITS are class 1E qualified to the applicable requirements of References 1.2.1.1, 1.2.1.2, 1.2.1.3, 1.2.1.4, and 1.2.1.5, and in accordance with the environmental conditions of Reference 1.2.2.4.

However, the computer and associated wiring is non-Class 1E.

The RCP current and potential transformers and watt transducers of the void fraction trending subsystem are high quality commer-cial grade components.

RCS cold leg temperature elements and RCS pressure transmitters are original plant equipment qualified in accordance with the TMI-1 licensing basis.

Wiring for the void l

fraction trending subsystem l

is non-1E.

All electrical work is performed in accordance with Reference 1.2.2.2.

Conduit routed inside containment will be supported as seismic Class I using new and existing supports installed in accordance with Reference 1.2.2.7.

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1.3.6 Structural Design l

l Equipment is designed to meet the requirements of Reference 1.2.1.2.

Tubing supports are designed in accordance with I

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t SD0 662C (DIV. II)

Rev. 1 I

Page 10 i

Reference 1.2.2.3.

Conduit supports are designed in accordance with Reference 1.2.2.7.

1.3.7 Quality Assurance The RCITS is to be installed, tested and inspected in accordance with the GPUN Operational QA Plan, Rev. 0 (Reference 1.2.2.1).

The water level trending subsystem is "Important to Safety" and

" Nuclear Safety Related".

void fraction trending subsystem is "Important to Safety" only.

t 1.3.8 Computer Displays Design The primary sources of computer display data are analog points from the system data base which (for RCITS purposes) have been labelled Group A data and Group B data.

Their point numbers and descriptors are:

Group A (Level) Data Al A466 RC Hot Leg A Level A2 A468 RC Hot Leg B Level A3 A467 Reactor Vessel Head Level 1 A4 A469 Reactor Vessel Head Level 2 Group B (Void Fraction) Data B1 C4018 Void Fraction A1 B2 C4019 Void Fraction A2 B3 C4020 Void Fraction B1 84 C4021 Void Fraction B2

_e___-,-_.---,.~..m

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

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9 SDD 662C (DIV. II)

Rev. 1 Page 11 Other sources of data are the following points:

A427 RCP A Power A428 RCP B Power A429 RCP C Power A430 RCP D Power C1679 Pump Running Index L2901 Reactor Trip The values for Hot Leg and Reactor Vessel Head levels will be derived from signals which have been compensated for primary system temperature and reference leg temperature in the Foxboro Signal Conditioning Cabinets.

The values for void fraction will be those calculated by the on-line application software program VOIDF.

The program uses RCP power, RCP status (pump running index) and RC inlet temperature as inputs.

RCP power values are derived from watt transducers associated with each RCP motor.

The pump running index is calculated by the NSS Application Software (NAS) program PMPIN.

PMPIN uses RCP motor breaker status contacts to determine the status of each pump.

The reactor trip status is calculated by the Process Computer's Trigger Task TT:RTP.

TT:RTP uses isolated reactor trip signals from RPS Channels A through D to determine reactor trip status.

At any given time the operator will view either Group A or Group B data.

Depending upon plant operating status, there will be times when the display of Group A or B data on RCITS displays will not be meaningful.

Group A (Level) data will be meaningful only when all RCPs are secured.

Group B (Void Fraction) data for an RC cold leg will be meaningful,only when the associated RCP is running.

To reduce the likelihood of confusion resulting from the viewing of data which is not meaningful when one or more RCPs are running, Group A data will be given a " bad" quality tag, and a request for its value will result in a display of a series of dots

(....).

This indication of quality and value will be the result of an automatic deletion of Group A points from scan.

The deletion from scan (and the return to scan when all RCPs are off) will be performed by the Application Software Program SGHUCD.

The same indications will be used for an RC cold leg's void frac-tion point when the associated RCP is secured.

Assignment of quality in this way is based on a check in VOIDF of the value of

SDD 662C (DIV. II)

Rev. 1 Page 12 the pump running index.

Furthermore, the void fraction for a cold leg will not be calculated if the associated pump is not running.

The decision as to whether or not to calculate void fraction is made in the Executive Program VOIDFR.

Table I summarizes the above information and the voio fraction calculation frequency.

TABLE I RCITS DATA INTERPRETATION GROUP A GROUP B VOID PLANT (LEVEL)

(VOID FRACTION) FRACTION OPERATING DATA DATA CALC.

CONDITION MEANINGFUL?

MEANINGFUL?

FREQUENCY No Rx Trip No Yes 6 min.

All RCPs ON (Normal Operation)

Rx Trip No Yes 30 sec.

All RCPs ON Rx Trip No Yes "ON" 30 sec.

1-3 RCPs ON RCPs No "OFF" RCPs Rx Trip Yes No N/A No RCPs ON The displays which may be used to present RCITS information to the control room operator are described below.

1.3.8.1 Single Point Displays (SPD)

The operator will have available for single point display any of the 14 variables listed above.

These variables will be accessible in the usual way via the Single Point Function Select key and point identification numbers.

When accessed by SPD, Group A (Level) data will have an indica-tion as to the meaningfulness via the indicated value and quality for each point.

When the data is not meaningful, i.e.,

wnen one or more RCPs are on, the quality for all four levels will be indicated as bad and the values will be indicated as a series of dots

(....).

9 SDD 662C (DIV. II)

Rev. 1 Page 13 When accessed by SPD, Group B (Void Fraction) data will also have an indication as to meaningfulness via the value and quality indications.

When an RC pump is secured, the quality indicator for associated cold leg's void fraction point will be set to bad, and the void fraction value will be indicated as a series of dots.

1.3.8.2 Group Displays 4

The operator will have available the RC Inventory Tracking Group Display shown in Figure 3 This display will be available in tne usual way via the Group Function Select Key.

The display will be one of the displays in the Reactor Coolant Inventory Group Display Area.

RC pump power is included in the group display because it is the major input to the void fraction calculation and can be used to corroborate an unexpected value for void fraction.

Pump Running Index is included because it can indicate or confirm which data, Group A or B, is currently meaningful.

The index can also be r

used as an additional corroborator of an unexpected value for void fraction.

Reactor Trip status is included as a reminder of

[

the update rate of the void fraction values.

(See Table 1).

The layout of data on the display is somewhat arbitrary and can 5

easily be changed.

The layout chosen for Figure 3 was based on the following considerations:

1.

Blocks of data are separated to enhance data search and find.

2.

The most important data is at the top.

Level monitoring (Group A) data is given highest priority, even though most of the time during normal operations the RCPs will be running and the data will not be meaningful.

f l

i 3.

Void fraction (Group B) data is next in importance and l

position.

4.

The major inputs to the void fraction calculations are next, in ode block.

5.

At the bottom, in an easily found location, is data (pump running index) which indicates whether Group A or Group B data is meaningful.

SDD 662C (DIV. II)

Rev. 1 Page 14 The display of Group A and B data meaningfulness will be the same as described in Section 1.3.8.1, When meaningful, the data will have a normal appearance; when not meaningful, the quality will be bad and the value will appear as a series of periods.

1.3.8.3 Trend Displays The operator will have available historical data trend displays which present a history of level and void fraction values (Group A and B data).

These displays will be available via the Long Term Storage and Retrieval (LS&R) Function Select key.

These displays will only be available on CRT #3.

1.3.8.3.1 Display Content Two historical data trend displays will be available to the operator.

One of the two displays is titled "RC Hot Leg & RV Levels" and will contain four historical data trend graphs, one graph for each of the four level variables in Group A.

The other display is titled "RC Cold Leg Void Fractions" and it also con-tains four graphs, one graph for each of the four void fraction variables in Group B.

When it appears on the screen after it has been requested by the operator, the display will contain historical data which has been recorded during the previous two hours and eight minutes.

The display will then be updated with new data at 30 second intervals (post-reactor trip), with the oldest data appearing to slide off the screen as new data is added.

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1.3.8.3.2 Display Selection To obtain the displays, the' operator first depresses the LS&R Function Select key, at which time the operator will be presented with a menu (Figure + ) on which a data eerry for display selec-tion may be made.

On the menu are listed two displays with corresponding display numbers.

To obtain one of the displays the operator presses the numeric key corresponding to the desired display and then presses EXECUTE.

If no display number is entered, the screen will default to Display #1 after EXECUTE is depressed.

To cancel the display, the CANCEL button should be depressed.

If one of the two displays is on the screen, and the other display is desired, the operator may either use the NEXT PAGE/ PREV PAGE

, ~ _

SDD 662C (DIV. II)

Rev. 1 Page 15 buttons, or cancel the current display and request the other display in the manner described above.

An incorrect entry will result in a yellow reverse video data entry field when EXECUTE is depressed.

1.3.8.3.3 Display Format The historical data trend display will have a format similar to the Data Trend Function display, or a strip chart recorder out-put.

,The displays will appear approximately as shown in Figures 6 and G.

The data will be plotted in four separate vertical rec-tangular boxes or charts.

The boxes and the variable trace incide each box are four different colors.

The colors, from left to right, are white, yellow, magenta and cyan.

Located above each box is a name for each trace.

Also above each box is displayed the current value for each variable as a floating point decimal number with one digit to the right of the decimal point.

The traces inside each box will consist of full intensity dots or data points at the appropriate location relative to the scale at the bottom of the box.

Also, half-intensity shading will be pro-vided from the zero points on the left-hand side of each box to each full-intensity data point.

New data points will be added at the top of each box.

(The plot rate will be displayed on the bottom line of the display).

The older points will be moved down with addition of each new point until they reach the bottom of the chart boxes, where they are finally pushed off the display.

The oldest value on the display will be two hours eight minutes old.

In the upper right-hand corner of the display is displayed the current date and time.

Directly under the current time, the time associated with the newest data on the display is shown.

On the middle right-hand part of the display the mid-point time of the chart is displayed.

On the lower right-hand part of the display is displayed the time associated with the display's oldest data.

The point number, description and et?ineering units for each variable being trended is listed under the rectangular boxes.

This information is displayed in the same color and sequence as the boxes that provide the data trend display for each variable.

Also listed is the zero and full scale value for each variable.

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O SDD 662C (DIV. II)

Rev. 1 Page 16 For variables A1 and A2, zero and full scale values are 0 and 50 feet, respectively.

(Only 98.3% of the scale will be used).

For variables A3 and A4, zero and full scale values are 0 and 15 feet, respectively.

For variables B1-B4, zero and full scale values are, respectively, 0 and 100 percent.

Running lengthways down the middle of each rectangular box is a line the same color as the box which is the half-scale indication for each box.

1.3.8.3.4 Display Data Interpretation The " meaningfulness" of both Group A and Group B data will be indicated on the historical data trend display.

When either Group A or Group B data is not meaningful, a series of dots extending from the left-hand side of the box to the right-hand side will be displayed.

The dots will be blue in color.

The dots will be spaced apart in the horizontal direction the width of one character position.

In the vertical (time axis) direc-tion, the dots will be spaced apart the height of one character position.

Al so, the value at the top of a box will be replaced by a series of dots when the box's variable is currently not meaningful.

An example which illustrates a case where historical data for the most recent hour was not meaningful is shown by the left-most box of Figure 6.

When the quality of Group A or B data is bad, this will be indi-cated on the trend display by a value of 0.0 and no plotting of data.

This treatment of bad data is the same as is performed by the Data Trend Function.

1.4 SYSTEM PERFORMANCE CHARACTERISTICS 1.4.1 Process Data Equipment connected to the primary pressure boundary is subjected to the following conditions:

Pressure 0-2500 PSIG Temperature 50*-650*F Boron Conc.

0-2270 PPM 1.4.2 Environmental Performance 1.4.2.1 Equipment inside the Reactor Building is subject to the following conditions:

1 SDD 662C (DIV. II)

Rev. 1 Page 17 Normal Conditions 40 year Base Temperature 130*F Relative Humidity 100%

Pressure Atmospheric Radiation 100 mR/hr 3.5 x 104 R/40 years Accident Conditions Temperature (Max.)

275'F Relative Humidity 100%

Pressure (Max) 50.6 PSIA Radiation 2x 107 Rads total Chemical Spray 9.5 pH l

1.4.2.2 Equipment in the Control Building is subject to both normal and accident conditions as follows:

40 year Base Temperature 75*F Relative Humidity 65%

Pressure Atmos.

Radiation 10 mR/hr R/40 yr Negligible /40 years 1.5 SYSTEM ARRANGEMENT The waler level subsystem of the RCITS is located within the Reactor Building and Control Building of Three Mile Island Nuclear Station Unit No.

1.

System piping and tubing is totally within the Reactor Building.

Piping and tubing are routed from the reactor vessel head area and inside the D-rings to instru-ments on racks located outside the secondary shield wall at ele-vation 281'-0".

Electrical cabling transmits signals from the instruments on the racks inside the Reactor Building to the Control Building.

The plant computer is used to indicate RCS hot leg and reactor vessel water levels.

The void fraction trending subsystem is located within the Control Building and the Turbine Building.

The RCP current and potential transformers are located in the switchgear room at ele-I vation 322' of the Turbine Building.

Electrical cabling transmits these signals to RPS-associated watt transducers in the Control Building.

From here Class 1E isolators transmit the signals to the plant computer.

SDD 662C (DIV. II)

Rev. 1 Page 18 1.6 INSTRUMENTATION AND CONTROLS t

A detailed description of instrumentation and controls is in-cluded in section 1.3.1 of this SDD.

The following are addi-tional details:

Differential pressure transmitters are installed with five valve manifolds.

The design of the indicator, computer displays and location of this instrumentation is subject to a human factors engineering review.

1.6.1 Instrument Ranges Instrument Operating No.

Use Range i

RC-LT-1033 Hot Leg Level A 0-50 FT RC-LT-1034 Hot Leg Level B 0-50 FT i

RC-LT-1035 Reactor Vessel Level 1 0-15 FT RC-LT-1036 Reactor Vessel Level 2 0-15 FT RC-TE-1033 and 1034 Density Compensation 70-250*F of reference leg fluid RC-TE-1054 and 1055 Density Comp. of RCS fluid 200-700*F RC-TE-1052 and 1053 Cold Junction Ref. Temp.

40-275*F 1.7 SYSTEM INTERFACES i

1.7.1 Electrical Distribution Systems The interface with the vital busses is via the existing 1E f

qualified power supplies provided with the (Foxboro) Signal Con-ditioning Cabinets A2 and B1.

Reactor coolant pump power is obtained from the RCP Power Monitor

(

Rack located at the 322' elevation of the Control Building.

Pump status is obtained from the associated switchgear.

The Bailey e

855 computer is powered from inverter IE (which receives vital power from either station battery IC or diesel generator IA) with backup vital power provided from diesel generator 1B.

The ModComp computer receives power from an electrical bus which is backed up by diesel generator 1B.

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SDD 662C (DIV. II)

Rev. 1 l

Page 19 1.7.2 Connections to the Primary Coolant and Decay Heat Piping f

Connections to the primary coolant loops via the High Point Vent piping are made through 1/2" tubing which is within the capacity of the makeup pump in the event of tube line breaks.

The tie-in to the decay heat drop line is made through a 3/8" hole drilled into the 12" diameter drop line.

The RCITS interfaces with the RCS Loop A and B High Point Vents, and Reactor Vessel head vent modification, the decay heat drop line, i

~

Double root valves are used at these connection points.

I Stress analyses are performed on the existing piping and the con-nections to confirm that the components are not overstressed.

1.7.3 Containment Penetrations Instrument cables for the new water level measurement instruments utilize existing spare conductors in electrical penetrations 204E 205E.

1.7.5 Computer System level data is input to the plant computer for display pur-poses.

System void fractions are calculated by the computer from RCP power inputs and then retained for display.

2.0 SYSTEM LIMITATIONS, SETPOINTS, AND PRECAUTIONS 2.1.1 The indications for hot leg water level of primary loop

'A',

hot leg water level of primary loop

'B',

reactor vessel head water level

'1',

and reactor vessel head water level

'2' are use-ful when the reactor coolant pumps are off.

These indications are provided by the plant computer during all modes of plant operatior..

4

SDD 662C (DIV. II)

Rev. 1 Page 20 2.1.2 During reactor vessel head removal, part of the water level measurement system must be removed.

Each of the reactor vessel head water level tubing runs bridge from the service structure to floor elevation 347'0".

Removable tubing sections are provided with a break flange on one side and a tubing con-nector on the other side.

These removable sections are located downstream of RC-V62A and 62B and must be removed before the reactor vessel head is removed.

2.1.3 The void fraction trending subsystem is useful when the RCP's are running.

These indications are provided by the plant computer during all modes of plant operation.

3.0 OPERATION The_ Reactor Coolant Inventory Tracking System (RCITS) is not required to monitor normal operation, heatup or shutdown.

Operation of the RCITS is only required during abnormal or emergency conditions and to monitor recovery from such con-ditions.

~ '

3.1 INITIAL FILL The initial fill of the RCITS system requires that all instrument tubing high points be flooded.

Instrument test valves at the instrument racks and fill valves at the reference leg condensate pot have been provided for the initial fill operation.

3.2 START UP No automatic or manual devices are required to start the RCITS system.

This system is continuously, operational during all modes of plant operation.

3.3 NORMAL The RCITS is continuously operational during all modes of opera-tion.

L 3.4 SHUTDOWN During plant shutdown the RCITS may be recalibrated to assure correct operation.

Each instrument is provided with manifold test valvec at their instrument rack location for calibration purposes.

Calibration of the electronics por-tion of the RCITS can be

SDD 662C (DIV. II)

Rev. 1 Page 21 I

accomplished at the Foxboro cignal conditioning cabinets at any l

time.

3.5 DRAINING Instrument blowdown valves are provided at the instrument rack which allow draining of the tubing.

3.6 REFILLING Refilling is the same as initial fill (paragraph 3.1 ).

High points in the RCITS should be verified filled during each refueling opera-i tion.

l 3.7 INFREQUENT OPERATIONS The RCITS will provide RCS water level trending following a loss of the Reactor Coolant Pumps.

Only one abnormal procedure is affected by the availability of the RCITS.

During natural circulation cooldown, the RCITS provides an indication of whether a bubble has formed in the hot leg or vessel head.

The following guideline can be used in OP 1102-16 "RCS Natural Circulation Cooling".

" Reactor coolant head voids may be evidenced by a large rapid increase in pressurized level or by an indicated head level less than full".

3.8 TRANSIENT OPERATIONS The RCITS 'is designed to monitor RCS inventory transients.

Thus, the primary usefulness of the RCITS is during emergency operating conditions.

The following guidelines provide confirmatory infor-l mation to other ICC instrumentation, which is tc be evaluated by the control room operator in performing plant recovery operations from abnormal transients.

3.8.1 RCP Bump / Restart Guidelines If the hot leg level is 6 feet below full or the head level is 3 feet below full and trending downward consider bumping the pumps prior to restarting them.

Basis:

Restart of the RCPs with substantial steam voids in the hot leg or head will result in a large pressurizer level and/or pressure response in the plant.

When steam voids are indicated, the RCPs should be bumped I

SDD 662C (DIV. II)

Rev. 1 Page 22 first to reduce the void volume.

These actions would be taken regardless of the RCS cooldown rate.

Collapse of either a head bubble or hot leg bubbles within these volumes will result in a pressurizer level drop of about 70 inches.

3.8.2 If hot leg level is less than 6 feet from the top of the hot leg evaluate whether primary to secondary heat transfer is available.

Basis:

A level of 6 feet below the top of the hot leg indica-tes that single phase natural circulation is unlikely since the U bend is voided.

Attempts should be made to restore primary to secondary heat transfer.

3.8.3 EFW Operation Evaluate the EFW flow rate if the het leg level is less than 19 feet below full.

Consider if EFW flow should be maintained above 450 gpm (225 per OTSG) until the 95% OTSG level setpoint is reached.

Basis:

If hot leg (and hence tube region) level is below the EFW flow injection point, then EFW flow should be established to assure boiler condenser cooling.

The use of the hot leg level in this case is a diverse indication from incore thermocouples and subcooling margin.

3.8.4 HPI Operation a.

Evaluate running all available HPI pumps at full flow if hot leg level falls 21 feet below full.

Observe all of the HPI throttling criteria.

b.

Evaluate running all the HPI pumps if the RCPs are running and RCS void fraction is continuing to increase.

Basis:

Three HPI pumps will not be run at all times.

If level decreases below the point where boiler-condenser cooling should be effective, then system refill should be aided by additional HPI flow.

Running 3 HPIs at too high a level may cause repressurization of the RCS.

Three pumps are unde-

SDD 662C (DIV. II)

Rev. 1 Page 23 sirable during water solid (i.e., feed and bleed) since the RCS pressure will be higher than if only two pumps are operating.

3.8.5 PORV Operation If hot leg level drops below the surge line elevation, 42 feet below the top of the hot leg, evaluate opening the PORV and leaving it open until LPI is in operation.

Do not open the PORV unless a source of water addition is available to the RCS (HPI, LPI or CFTs).

Basis:

Once the surge line is uncovered, the PORV will be relieving steam.

Steam relief provides the most effective means of cooling and depressurization from a given inventory loss.

This action will even be effective under conditions where all HPI has been lost since it maximizes the chances of reaching CFT actuation pressure.

If no makeup is available to the RCS, then inventory losses should be minimized while the operators attempt to provide a source of water to the RCS.

Note that the PORV is also opened by existing procedures when the RCS pressure reaches 2300 psig and these two actions are complimentary to each other.

3.8.6 The following notes should be added to the Abnormal Transient Procedures:

a.

Hot leg level indication is invalid when the hot leg high point vents are open.

b.

RCS void fraction is only valid when the RCPs are operating.

4.0 CASUALTY EVENTS AND RECOVERY PROCEDURES Neither the void fraction nor hot leg level instruments initiate any automatic control actions.

Their failure in either the high, low or intermediate position will require detection by comparison with other instruments.

This situation is true for the failure of any indication and does not represent a unique situation for the operator to deal with.

Failure of the instrument piping associated with the RCITS does not result in a LOCA, but does represent a substantial leak.

SDD 662C (DIV. II)

Rev. 1 Page 24 None of the indications provided by the RCITS are required or relied upon to recover from such a failure.

For example, a break in the hot leg level instrument tube would result in a leak within the capacity of the normal makeup system requiring a plant shutdown.

Level from that loop could read low.

However, other plant indications such as saturation margin, makeup tank and pressurizer level, makeup flow, RCS pressure, RB sump level, con-tainment temperature and pressure, and void fraction would indi-cate that both. hot legs were full.

5.0 MAINTENANCE 5.1 MAINTENANCE APPROACH The RCITS is installed with double isolation valves at each instrument tap location.

When these valves are closed access to piping and tubing is provided to allow maintenance of the other valves and connections.

5.2 CORRECTIVE MAINTENANCE Most corrective maintenance on the RCITS will be with respect to leakage problems.

Tnese leaks are expected to occur at flange joints and across valve seats.

As covered in 5.1, above, corrective maintenance which needs to be performed, in most cases, can be performed by closing the iso-lation valve upstream.

This precludes the requirement for draining the RCITS while maintenance is in progress.

5.3 PREVENTIVE MAINTENANCE No preventive maintenance is normally anticipated for system equipment.

Surveillance and associated maintenance shall be per-formed in accordance with the manufacturer's recommendations.

Normal Technical Specification surveillance requirements will be observed.

All valves in the system that provide fluid isolation should be internally inspected at least once every five years to assure integrity of the seating surfaces.

The same preventive main-tenance interval should be applied to all flange joints.

Snubber oil levels should be checked as required by manufacturers main-tenance instructions.

Normal routine maintenance should be per-formed in accordance with established procedures and vendor recommendations.

SDD 662C (DIV. II)

Rev. 1 Page 25 l

5.4 INSERVICE INSPECTION AND TESTING Testing / calibrating of the level instrumentation will be per-formed during each refueling by simulating the compensating 4

signals, as done for existing similar level instrumentation (e.g.

i pressurizer).

L The inservice inspection program requires periodic non-I destructive examinations be performed during plant outages.

The type extent and frequency of examinations will be specified in accordance with Procedure 6150-ADM-3272.01 of the GPU Nuclear Inservice Inspection Manual (Ref. 1.2.2.10).

I 6.0 TESTING The following tests must be accomplished for an acceptable RCITS I

system.

i 1.

Hydrostatic pressure test of piping and tubing system.

2.

Functional test as required by the control system's supplier (Foxboro Spec. 200).

7.0 HUMAN FACTORS l

1

-l GPUN Human Factors Engineering has reviewed the RCITS design.

A review of display type, information and format has been conducted in conjunction with Plant Analysis.

Plant Analysis input for the j

displays has been incorporated into the design and no new hard-ware interface is involved.

All displays recommended by Plant

[

Analysis are in accordance with the principles of human engi-t neering.

A post-construction walkdown will be performed to

[

assure that scale, labels, and other man-machine interface items are acceptable.

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SDD 662C (DIV. II)

Rav. 1 Page 26

%REA 3 GROUP 37 RC INVENTORY TRACKING A466 RC Hot Leg A Level A468 RC Hot Leg B Level A467 Reactor Vessel Head Level 1 A469 Reactor Vessel Head Level 2 C4018 Void Fraction Al C4019 Void Fraction A2 C4020 Void Fraction B1 C4021 Void Fraction B2 A427 RC-P-1A Power A428 RC-P-1B Power A429 RC-P-1C Power A430 RC-P-ID Power L2901 Reactor Trip C1679 Pump Running Index Figure J RC INVENTORY TRACKING GROUP DISPLAY

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n Exhibit A B&W Doc.10 47-1149188-01 " Summary Information Package RCS Coolant Inventory Trending (CIT) with RC Pumps Operating".

Exhibit B Description of Material Applicable Criteria B&W 00c. ID 47-1149188-01 " Summary Information Package b, c, d & e RCS Coolant Inventory Trending (CIT) with RC Pumps Operating" As stamped in the report and as noted below:

Page 6 Section 2.2 Page 7 In its entirety r

Page 8 In its entirety Page 9 In its entirety Page 10 In its entirety Page 13 Paragraph 2 of Section 3.1 and Section 3.2 Page 14 Section 3.2 Page 15 In its entirety Page 16 Table 3.1 and notes Page 17 Figure 3-1 Page 18 Figure 3-2 Page 19 Figure 3-3 Page 20 Figure 3-4 s

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