ML19210B488

Forwards Addl Info Re Overpressure Protection Sys,In Response to NRC 771111 Request

ML19210B488
Person / Time
Site:	Three Mile Island
Issue date:	01/13/1978
From:	Herbein T METROPOLITAN EDISON CO.
To:	Reid R Office of Nuclear Reactor Regulation
References
GQL-0049, GQL-49, NUDOCS 7911080718
Download: ML19210B488 (8)

Text

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• NRCPon'u 195 U.S. NUCLEAR REGULATORY COMMISh N OoCKET NUMBE A t2 76) fd . 3

''""""

N.'.0 DISTRIBUTION Fon PART 50 DOCKET MATERIAL TO:R. W. Reid FROM: *' ' "

Met Ed 01/13/78 Reading, Pa. 19603 J. G. Herbein oATE afCEivEo01 18/78, 2-TTTE m OsoTonizEo ency INPUT FORM NUM8ER CF COPIES RECEIVED

.EClilGIN A L MC LAsSIFIE D QCorv /S/6A/W cEsCRIPTION " ' "'

Response to NRC's 11/11/77 ltr...

consisting of addl info re the Overpre.ssure Protection System for Unit 1. . . .w/att drawin gs

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REACTOR VESSEL OVERPRESSURIZATION DISTRIBUTION PER G. ZECH 10-21-76 PLANT NAME* THREE MILE ISLAND UNIT # 1 0Mi- )j Cm 02/01/78Se 2fdMMn//Ml78 /SerAeed6S -/o 5t'au 29 06 C#dCkt!'O SAFETY , ' FOR ACTION /INFORMATION /3 r./P "7D J/(f( fh2'a/r#44, BRANCH CHIEF: (SY 7') WJD Att c7W4Rf Adk*t*/VL' 4.7AS eM.Y L7xC . .,0 0T :

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POST OFFICE BOX 542 READING, PENNSYLVANI A 19603 TELEPHONE 215 - 929-0601

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January 13, 1978 GQL 0049 ..

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Director of Nuclear Reactor Regulation [ '4 1.- 't j Attn: R. W. Reid, Chief >-

Operating Reactors Branch No. k ~4 /$j%

U. S. Nuclear Regulatory Ccmsission  %  %,

Washington, D. C. 20555 F3 f)

Dear Sir:

' "

Three Mile Is1 sad Nuclear Station Unit 1 (TyI-1)

Docket No. 50-289 -

Operating License No. DPR-50 Overpressure Protection System Your letter of November 11, 1977, stated that the overpressure protection system for TMI-1 currently installed in ec=bination with the proposed changes does not meet all the criteria established by the NRC, and that additional informaticn and proposed Technical Specifications should be submitted by December 29, 1977 In an attempt to understand your concerns and to clarify portions of our March 22, 1977, submittal, members of my staff met with members of your staff via telecon on December 15 and 22, 1977 As a result of these telecons, Met-Ed agreed to submit the various options considered with an evaluation of each option where appropriate, as well as the additional information requested, by January 15, 1978. The following respenses are hereby submitted:

.

1584 179 780320003

.

R. W. Reid, Chief

-

1/13/78 GQL 00h9

. .

I. ODTICUS EVALUATED FOR OVERPRESSURE PROTECTION

• A. Decay Heat Removal System (Re: GAI Dvg. C-302-6h0/TMI-1 FSAR Fig.

9-10)

The decay heat removal system as presently installed has no capability to protect the RCS from an overpressurization transient. Of the system piping available the 10" discharge lines are checked against backflow by DH-V22A/3, and the 12" suction line is blocked by DH-71 and DH-V2 which trip closed at a RCS pressure of h00 psig. Since the decay heat removal. system was not designed for an RCS over-pressurization, this option is not acceptable.

3. Makeup and Purification System (Re: GAI Dvg. C-302-661/ TMI-1 FSAR Fig. 9-3)

1. Install h" manual block valves on each of the two (2) h" discharge lines upstream of the motor operated HPI valves MU-V16A/3/C/D. This option would cost on the order of $100,000 and could be scheduled for the 1980 refueling outage.

2. Install a 21/2" manual block valve with a relief valve on each of the four (h) 2 1/2" HPI lines , downstream of the motor operated HPI valves MU-VI6A/3/C/D. This option would cost on the order of $200,000 and could be scheduled for the 1980 refueling cutage.

3. Lock closed MU-V77A/3 such that with MU-PIB running (normal mode of operation), no HPI flow is available. This option is undesirable since it restricts operating flexibility in that MU-PIA cannot be placed in operation,

h. Install relief valves between the MU pumps and HPI valves.

This option is not acceptable since the overpressure protection relief valve set points would necessarily be less than the normal system discharge head.

5. Limit the level in the Makeup Tank to 66". This option restricts flexibility in operations during norme.1 plant cooldown, and is therefore undesirable.

• Assuming the following:

Initial Conditions - Normal charging ilov via MU-V17

,, Normal letdown established Occurrence - MU-V16 (A/3/C/D) opens Failure - E4 Relief Valve (RCR-V2) fails to open 1584 180

.-

R. W. Reid, Chief 1/13/78

, , GQL 00h9 C. Pressurizer Modifications - Install an additional block and EM relief valve en top of the pressurfter.' This option, if physically possible in the space limitations, vould be expensive (approximately

$h00,,000), and would take en the order of 2 to 21/2 years to ac-complish. Installation could probably be accomplished during an extended 1981 refueling outage.

D. Ferformance of the following actions:

1. Assure the MJ-V16A/B/C/D in closed position

2. Open the MU-716A/3/C/D breakers at i 300 0 F and 1 1500 psig

3. Lock the breakers in the open position - Key controlled by shift superviscr.

h. Lock the MU-V16A/B/C/D handvheels - Key controlle.d by shift supervisor.

5. Limit the pressurizer level to 1220" This option is the most desirable of the options discussed in that limited administrative and hardware changes are required. These changes could be implemented within a reascnably short period of time.

Met-Ed proposes to use option "D" above. The incredible scenerio which would have to occur to decrease the overpressure protection provided is as follo,vs:

Assuming the initial conditions previcusly stated, an operator would have to procure the valve handwheel keys from the shift supervisor, unlock a handwheel and open the valve, or obtain the breaker keys frcm the shift supervisor, close a breaker, and rtart the motor operator to open the valve. These actions vculd be in violation of several procedures and would be carried out with the shift super-visor's knowledge.

II. Electrical Circuit and Lecie Diagrams The following electrical circuit and logic diagrams requested in your letter of November 11, 1977, are attached in order to facilitate your review:

Dwe. No. Description Bailey D556139D -

Aux. System, Digital Logic, Temp. Loop Bailey D55h568 -

Aux. System, Analog Logic, Press. Loop Part 1 Bailey D55h566G -

Aux. System, Analog Logic, Ccolant Temp.

Loop Part 2 ,

Bailey D8032702K -

Aux. System, Det. Schematic, R.C. Part 2 3ailey D8032703G -

Aux. System, Det. Schematic, R.C. Part 3 Bailey D803270hJ - Aux. System, Det. Schematic, R.C. Part h GAI SS-209-069 - 3.C. Pressurizer Pressure Switch RC3-PS8, .

Aux. Relay 63X/RC30?S8 GAI SS-209-03h -

Pressurizer Electrcmatic Relief Vv. RC-RV2 GAI SS-208 h26 -

Pressurizer Relief Block Vv. RCV-2

.

R. 'J. Beid, Chief

,

-h- -

1/13/78 GC,L 00L9 Also attached are the electrical elementary diagrams for the EPI equipment.

These are,

• Dve. No. Descrintion GAI SS-208-213 -

Make-up Pump MU-PIA GAI SS-208-21h - Make-up Pump MU-PIC GAI SS-208-215 - Make-up Pump MU-PIB GAI SS-208-216 - Make-up Pump MU-PIB GAI SS-208-217 - Make-up Pump Scheme GAI SS-208-kh2 - Emer. Make-up Valves MU-V16A/B/C/D To assure prope$ alignment of the overpressure protection system during plant cooldown, your November 11, 1977, letter requires an enabling alar =

which monitors the system enabling switch and the position of the isolation valve upstream of the PCRV. Presently, the TMI-1 overpressure protection system enabling switch, NDTT switch, shown on GAI SS-209-069, has two positions, OFF or AUTO. In the OFF position, the overpressure protection system would be disabled (Re: Bailey Dvg. No. D556139D) . The installation of an additional contact to the NDTT switch which will alarm whenever this switch is in the CFF position is being engineered. This alarm vill be identified by " Pressurizer Electromatic Relief Valve Disabled". This modification will be completed by the end of the 1979 refueling outage. -

The pressurizer relief block valve, RC-V2, presently has indicating lights (OPEN or CLOSED) en the Control Room panel for valve status.

However, there is no alarm monitoring the status of this valve. The installation of an alarm for whenever RC-V2 is closed is being engineered.

This alarm vill annunciate as above, " Pressurizer Electromatic Relief Valve Disabled". This modification vill be accomplished concurrent with the NDTT switch-alarm modification above.

III. Prorosed Technical Suecifications Proposed Technical Specifications are under review by Met-E5 Technical Staff and Safety Committees, and should be submitted as formal Technical Specfication Change Requests prior to the 1978 refueling outage. These proposed specifications include the conditions for removal of the Electromatic Relief Valve from service for testing and maintenance, and system enabling temperatures and Electromatic Relief Valve setpoints. .

.

Sincerely,

.

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jl Herbein J. v.

Vice-President Generation JGH:RJS:jdp K.tachments k )f h \

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