ML20106C357

Forwards Revised Pages to 840706 Submittal (Sdd 662C Div II) Re Reactor Inventory Trending Sys & Revised Schedule Consistent w/841003 NUREG-0737,Item II.F.2 (Inadequate Core Cooling) Status Response

ML20106C357
Person / Time
Site:	Three Mile Island
Issue date:	02/06/1985
From:	Hukill H GENERAL PUBLIC UTILITIES CORP.
To:	Stolz J Office of Nuclear Reactor Regulation
References
RTR-NUREG-0737, RTR-NUREG-737, TASK-2.F.2, TASK-TM 5211-85-2020, NUDOCS 8502120232
Download: ML20106C357 (14)

Text

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GPU Nuclear Corporation NggIg7 Post Office Box 480 Route 441 South Middletown, Pennsylvania 17057 0191 717 944 7621 TELEX 84 2386 Writer's Direct Dial Number:

5211-85-2020 February 6, 1985 Office of Nuclear Reactor Regulation Attn: J. F. Stolz, Chief Operating Reactor Branch No. 4 Division of Licensing U.S. Nuclear Regulatory Commission Washington, D.C. 20555

Dear Mr. Stolz:

Three Mile Island Nuclear Station Unit 1 (TMI-1)

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

Attached please find revised pages to our July 6,1984(5211-84-2173)(SDD 662C Div II) submittal on the Reactor Inventory Trending System and a revised schedule consistent with our NUREG 0737 status response of October 3, 1984 (5211-84-2244). Amended responses to NRC Request for Additional Information dated June 14, 1983 and GPUN response of January 31, 1984 and July 6, 1984 is planned for submittal in March,1985.

Sincerely, ty D. Huki Director, TMI-1 HDH/spb cc: R. Conte J. Van Ylfet

()OY 0165A 8502120232 850206 PDR ADOCK 05000289 P

PDR GPU Nuclear Corporation is a subsidiary of the General Public Utilities Corporation

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Attachment 1 Revised pages to SDD662C Div. II RCS Inventory Trending System l Replacement Pages 6

10 11 16 18 23 25

'26 29 (Fig.5) 30 (Fig.6) h

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Attachment 1 Revision 2 to S00 662C Div. II (July 6, 1984/5211-84-2173)

SDD 662C (DIV. II)

Rev. 2 Page 6

-1.3.1.2 Hot Leg Level Primary Loop B Differential pressure transmitter RC-LT-1034 is installed between an upper connection at the top of stean, generator RC-N-It'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.

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

' Thermocouple RC-TE-1055 senses reactor coolant system core exit-

' temperature and is' used to compensate for density changes in the reactor vessel head and hot leg fluids. Resistence 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 incere detector rack, Reactor Building elevation 346'-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, 4

E1. ; 32 2 '-0" .

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

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!' 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 lower connection upstream of valve DH-V-1. This instrument

measures the level from the bottom of the hot leg piping to the bottom of the RV head vent nozzle. l i

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S00 662C (DIV. II)

Rev. 2 Page 10 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 Dyerational QA Plan, Rev. 0 (Reference 1.2.2.1).

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

" Nuclear Safety Related". The void fraction trending subsystem is "Important to Safety" only.

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 A1 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 i Group B (Void Fraction) Data 81 C4018 Void Fraction IA B2 C4019 Void Fraction IB B3 C4020 Void Fraction 1C B4 C4021 Void Fraction ID e

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SDD 662C (DIV. II)

Rev. 2 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 Inden L2776. CRD Trip confirmed l The values for Not 14g 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 inden) 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 derived from CRD trip Confirmed, L2776, i

At any-given time the operator will view either Group A or-Group R 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 meaningf ul. Group A' (Level) data will be meaningf ul only when all RCPs are secured. Group B (Void Fraction)' data for an RC cold leg will, be meaningf ul .only when . the associated RCP is i running.

! To reduce'the likelihood or confusion resulting from the viewing

, of data which is not meaningful'when one or more RCPs are 4 running, Group A data will be given a "nad"~ 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 f rom scan (and the return' to . scan when all RCPs are of f )

will be- performed by the Application Sof tware 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 votDF of the value of 1

SDD 662C (DIV. II)

Rev. 2 1 Page 16 For' variables A1 and A2, sero and full scale values are 0 and 50

feet, respectively. For l l ' variables A3 and A4, sero and full scale values are 0 and 12 i feet, respectively. For variables 31-84, sero and full scale values are, respectively, 0 and 100 percent. l Running lengthways Jown the middle of each rectangular box is a line the same color as the box which is the half-scale indication ,

for each box.

t.3.4.3.4 Display Data Interpretation The " meaningfulness" of both Group A and Group B data will be indicated on the historical data trend display. When either r 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. Also, 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 lef t-most box of Figure 6.

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1.4 SYSTEM PERFORMANCE CHARACTERISTICS

! 1.4.1 Process Data Equipment connected to the primary pressure boundary is .

j _ subjected to the following conditions: i Pressure 0-2500 PSIG I i Temperature 50*-650*F Boron Conc. 0-2270 PPM i 1.4.2 Environmental Performance i 1.4.2.1 Equipment inside the Reactor Building is subject to the following conditions:  !

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SDD 662C (DIV. II)

Rev. 2 Page 18 1.6 INSTRUMENTATION AND CONTROLS 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 computer displays and location of l this instrumentation is subject to a human factors engineering review.

1.6.1 Instrument Ranges Instrument Operating No. Use Range RC-LT-1033 Hot Leg Level A 0-50 FT RC-LT-1034 Not Leg Level B 0-50 FT RC-LT-1035 Reactor vessel Level 1 0-1 2 FT t

- RC-LT-1036 Reactor vessel Level 2 0-12 FT l RC-TE-1033 and 1034 Density Compensation 70-250*F of reference leg fluid i RC-TE-1054 and 1055 Density Comp. of RCS

fluid 200-700*F l.

RC-TE-1052 and 1053 Cold Junction Ref. Temp.40-275'F 1.7 SYSTEM INTERFACES 1.7.1 Electrical Distribution systems l: The interface with the vital busses is via the existing 1E

qualified power supplies provided with the (Fosboro) Signal Con-j ditioning Cabinets A2 and 31.

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 sailey 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 15. The

ModComp computer receives power from an electrical bus which is backed up by diesel generator 18.

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I' SDD 662C (DIV. II)

Rev. 2 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. Additionally, threo !!PI pumps hould only be run if the RCS cooldown rate is less than 100 F/hr.

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 wnile 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.

c. RV head icvel indication is invalid when the head vent is open. l 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 comparisen 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 lean.

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SDD 662C (DIV. II)

Rev. 2 Page 25 5.4 INSERVICE INSPECTION AND TESTING Testing / calibrating of the level instrumentation will be per-formed during each refueling by simulating the compensating signals, as done for existing similar level instrumentation (e.g.

pressurizer).

The inservice inspection program requires periodic non-

' 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 Differential pressure transmitters and resistance temperature detectors associated with this modification have been qualified for in-containment service. As such, the qualified environmental barriers must be maintained throughout the maintenance and calibration cycles.

must be replaced eachSomecycle.of these barriers are consumable and Refer to manufacturer's instruction manual for specifics relative to maintaining the integrity of environmental barriers.

6.0 TESTING The following tests must be accomplished for an acceptable RCITS system. ,

1. Hydrostatic pressure test of piping and tubing system.

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

7.0 HUMAN FACTORS 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 l displays has been incorporated into the design and no new hard-l ware interface is involved. All displays recommended by Plant Analysis are in accordance with the principles of human engi-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)

R3v. 2 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 lA C4019 Void Fraction IB C4020 Void Fraction 1C C4021 Void Fraction ID A427 RC-P-1A Power A428 RC-P-1B Power A429 RC-P-IC Power A430 RC-P-ID Power 1 L2776 CRD Trip Confirmed i C1679 Pump Running Index Figure J RC INVENTORY TRACKING GROUP DISPLAY I

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Attachment 2 ICC Instrumentation' Schedule (RITS)

Rev. 2 a) Operating and Emergency Procedure Mods

• 2/85

,b) Submit Technical Specifications for ICC 3/85 Instrumentation

'c) Complete Installation of RITS completed.12/84 d) Complete Installation of Safety Grade SMM 3/85 e) Complete Testing and Calibration of RITS 3/85 f)CompletetrainingofR0/SRO Completed 12/84 g) Operational date of RITS Based on approval of NRC h) Environmental Qualification of RITS and 11/85 Incore Thermocouples**

• Pending review by NRC

• • Schedular extension to be submitted by January 31, 1985 0504e h

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