ML20078R598

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Forwards Util Presenting Alternate Solution for Plant Shielding (NUREG-0737,Item II.B.2)
ML20078R598
Person / Time
Site: Three Mile Island Constellation icon.png
Issue date: 11/10/1983
From: Baxter T
METROPOLITAN EDISON CO., SHAW, PITTMAN, POTTS & TROWBRIDGE
To: Chilk S
NRC OFFICE OF THE SECRETARY (SECY)
References
RTR-NUREG-0737, RTR-NUREG-737, TASK-2.B.2, TASK-TM NUDOCS 8311150221
Download: ML20078R598 (3)
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00CMETED SHAW, PITTMAN, PoTTs & TROWBRidiONEC A PARTNERSMIP OF PROFES$10NAL CORPORATIONS ISCO M STREET. N. W.

883 !& 14 M1 l}9 WASHINGTON. D. C. 20036

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RAM SAY O. POTTS. PC

( TWART L Pf7TMAN. PA

( EORGE F. TROwSRIDGE. PA SHELOON J. WEISEL. PC JOMM A. McCULLOUGM. PA J. PATRICK MtCREY. PA

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EDWARO O. YOUNG. Bil 4 - %, ANDREW etCMARO O.A.ELUS SAMP J. TMOMAS LENMART. PA TELECOPtER 0 f7I"p THOM AS E. CROCME R. J R.

(TEPMEN O. POTTS. PA JOMN E. CARRA GEPALO CMARNOFF. PA STEVEN L MELTZER.PC PM8UP J. MARv8T h NI[* wENOELIN A. WHtTE PM.LUP O. SOSTwica. Pc OEAnD.AuuCa.PC. (202) eaaaoes & saa.fiss ROBERTu,oOROOu STANLEv M. SARG

2. TIMOTMV MANLON. P C. JOHN ENGEL PA _

SARSARA J. MORGEN LESUE K. SMITH (C ORGE M. ROGERS.JR PC CMARLES S. TEMMIN. PA SONNIE S.GOTTUES vimons A S. RUTLgOog FRE 4 A. LITTLE. P C. STEPMEN S. MUTTLER PA RApeFAh sOO MCwARO H. SMAFFERMAN gayggggggp,ggggg JOMM S. RMINELANDER. PC WINTMROP N. BROWN. P C. OEBORAMS.SAUSER JANICE LEMRER-STEIN BRUCE w. CMuRCMiLL. Pc JAMES S. MAMUN. P C. (202)822-5072 SCOTT A. ANENSERG TRAVIS T. BRQwN. J R.

L Skit A. NiCMOLSON.JR., PA RANDAL 5. RELL PA _

CAMPSELL MsLLEFER RsCHARO H. MRONTHAL MARTIN O mRALL. PC ROSERT E. ZAMLER. PC PAUL M. TMOM AS STEPMEN 5.MEIMANN RICHARO J. KENDALL. PA ROSERT3.ROSSIMS.PC 7gggg SETM M. MOOGASIAN SANORA E. BRUSCA*

Jiv E. SILSEleG. PC STEVEN M. LUCAS. P C. SMEILA MCC. HARVEY BARSARA M. ROSSOTTI. P C. DAveOM.RUSENSTEIN.PC DELISSA A. RIDGWAY EBLEEN L BRowNELL 89-29 53 (SMAwLAw WSM) AMELA . ANDERSON GEORGE V. ALLEN.JR PA RfC,. t QALEN CA ELE . 8"A* LAW..

MENNETM J. MAUTMAN ALEXANDER O. TOMASZC2un FRE 9 ORASNER. P C. LYNN secefn L*SEY WILSON DAvec LAWRENCE MILLER PMrup O. PORTER Gk MENLY WESSTER. PA MATIAS F. TRAVIESO-DIAZ ~ FREDERICM L KLEIN NATHANIEL P. GRE EC. J R., PA VICTORIA J. PERRIN S STEVEN P. Pf7LER. MICHAEL A. SwlGER MARM AUGENSUCR P C. JOMN M. O NEILL JR. ELLEN SMERIFF 7RNEST L SLAmt.JR., PA JAY A. EPSTIEN RfCMA ELLEN RO J. PA RRE.NO A. FREDEL ANITA J. FINKELSTEIN CARLETON S. JONES. PC RAND L ALLEN MANNAM E. M. LsESERMAN E'LEEN M. GLEIMER THOMAS A. SANTER. PA EUSAGETM M PENOLETON COUNSEL SANDRAE.FOLSOM OAVs0 m.SAMR JAMIS M. SURGER. PA MARRY M. GLASSPtEGEL JUDITH A. SANDLER C.. SOwCOfN M,.m. TRAIN November 10, 1983 .R TER S O. RECT O,= NUM.ER Mr. Samuel J. Chilk Secretary U.S. Nuclear Regulatory Commission Washington, D.C. 20555 In the Matter of Metropolitan Edison Company (Three Mile Island Nuclear Station, Unit No. 1)

Docket No. 50-289 (Restart)

Dear Mr. Chilk:

Please find enclosed a copy of the following document, which includes information potentially relevant and material to matters under adjudication in the plant design and procedures phase of this proceeding, which is now before the Commission:

Letter 5211-83-280, October 21, 1983, H.D.

Hukill, GPU Nuclear, to J.F. Stolz, NRC, Alternate Solution for Plant Shielding _

(NUREG-0737, II.B.2).

Respectfully submitted,

/

Thomas A. Baxter Counsel for Licensee Enclosure cc: Service List TAB / lam b

UNITED STATES OF AMERICA NUCLEAR REGUIRIORY CDMISSICN BEECRE THE COMISSION In the Matter of )

)

ME'110FOLITAN EDISCN 03fPANY ) Docket No. 50-289

) (Restart)

PIhree Mile Island Nuclear )

Station, Unit No.1) )

SERVICE IJST Cbmi man Nunzio J. Pallad ho Dr. Reginald L. Gotchy U.S. Nuclear Regulatory Cm =4=sion Atomic Safet'.f ar:d Licensing Appeal Washington, D.C. 20555 Board U.S. Nuclear Regulatory Ca mission Canmissioncr Victor Gilinsky Washington, D.C. 20555 U.S. Nuclear Regulatory Cm =iasion Washingtcn, D.C. 20555 Ivan W. Smith, Esquire Chairman, Atcnic Safety and Licensing Cmm2.ssioner 'Itcnas M. Roberts Board U.S. Nuclear Regulatory Canmission U.S. Nuclear Regulatory Ca mission Washington, D.C. 20555 Washington, D.C. 20555 Cm missioner James K. Asselstine Sheldon J. Wolfe, Alternath Chaiman U.S. Nuclear Eegulatory Cm mission Atcmic Safety and Licensing Board Washington, D.C. 20555 U.S. Nuclear Regulatory Cm mission Washington, D.C. 20555 Ca missioner Frederick M. Bernthal U.S. Nuclear Regulatory Cr=miesico Mr. Gustave A. Linenberger, Jr.

Washington, D.C. 20555 Atomic Safety and Licensing Board U.S. Nuclear Regulatory Cm mission Docketing and Service Section Washington, D.C. 20555 Office of the Secretary U.S. Nuclear Regulatory Cm mission Richard J. Rawson, Esquire Washington, D.C. 20555 Office of Executive Legal Director U.S. Nuclear Regulatory Cm mission Gary J. Edles, Esquire Washington, D.C. 20555 Chauman, Atcmic Safety and Licensing Appeal Board John A. Ievin, Esquire U.S. Nuclear Regulatory Ca mission Assistant Counsel Washington, D.C. 20555 Pennsylvania Public Utility Cm mission P. O. Box 3265 Dr. John H. Buck Harrisburg, PA 17120 Atcmic Safety and Licensing Appeal Board Marjorie M. Aamodt U.S. Nuclear Regulatory Camission R. D. 5 Washingtcn, D.C. 20555 Coatesville, PA 19320

Douglas R. Blazey, Esquire Steven C. Sholly Chief Counsel Union of Concerned Scientists Department of Envirorrnental Resources 1346 Connecticut Avenue, N.W., #1101 514 Executive House, P. O. Box 2357 Washington, D.C. 20036 Harrisburg, PA 17120 ANGE/'IMI PIRC Ms. Iouise Bradford 1037 Maclay Street

'IMI ALERE Harrisburg, PA 17103 1011 Green Street Harrisburg, PA 17102 Chauncey Kepford Judith H. Johnsrud Ellyn R. Weiss, Esquire Er# m tal Coalition on Nuclear Power Harmon & Weiss 433 Orlando Avenue 1725 Eye St., NW, Suite 506 State Collece, PA 16801 Washington, D.C. 20006-es e

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GPU Nuclear Corporation ggIgf ,

Post Office Box 480 Route /41 South Micdletown, Pennsylvania 17057 0191 717 944 7621 TELEX 84 2386 Vuiter's Direct Dial Numben Office of NJ lear Reactor Reculation ~

At:n: J. F. Stolz, Chief Operating Reactors Branch No. 4 Division of Licensing U. S. NJ lear Regulatory Commission Washington, D. C. 20555

Dear Sir:

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

Operating License N . OPR-50 Docket No. 50-289 Alternate Solution for Plant Shielding (NUREG 0737, I1.5.2) ,

In our response to Generic Letter 82-05 (May 21,1982 and June 15, 1982), we indicated that the plant shielding modification involving remote valve operatcrs for certain Decay heat Removal (DHR) system valves would not be completec until startup frcm Cycle 6 refueling. By letter cated Sectem:er 20, 1982, GPUN provided justification for operation until Cycle 6 and a e:necule for delivery and installation of the DKR valve erators. This matter was brought before the NRC Commissioners via SECY-82-360 an: 3S4A and CEferral of this item was grantec by NRC letter dated January 13, 1953.

G UN has since that time continue: to work :: ne prc :se: S necul= Ou nas i-the process oevelopec an alternate solution :: :ne p:::lem wnien can in;r ve the schedule and will reduce complexity anc : st.

Attachment i provices c';r evaluation an cescri:-icr f One C:s: a icent shielding alternative selution wni:n cem nstrates tha ne pre: se:

medi'ication is tecnnically acce :able. Base: :- ir:reve: s:ne:ule an:

Ce:uced complexity, tne :: pese: to ificatie- is :re'erra:le.

Ease: :n tre a::ve, we recues y:ur exceciti:_s revie. ar.: concurre .:e oi--

'F.is newly ?r:00:8 mOcifi:2: ion in lieu cf e Irevi usly Orc; se:

notificatiCns in orter tnat engi9eering 9ay : ::ee:.

Sincerel .

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GPU Nt. clear Corporation is a subsidiary of the Generai ubli: Utilities Corporation

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POST ACCIDENT BORON PRECIPITATION EVALUATION I. Background GPUN studied the need for plant shielding in accordance with NUREG 0576 item 2.1.6.b .as modified by NUREG 0737 iter II.E.2. The stucy was described in Restart Report section 2.1.2.3 anc evaluatec in NJREG 0680.- The study concluded, among other tnings, that modifications were needed to address post LOCA boron precipitation.

Boron precipitation on fuel elements is pcstulated to occur due to post-accident water phase concentration in the reactor vessel. Since normal safety injection enters only the vessel cowncomer area (via the cold leg or core flood) a cold leg break may result in no forceo circulation through the core. Decay heat removal in this case is to be continued steaming from the vessel with increasing baron concentration.

2 This phenomena was evaluated by B&W with the discussion presented in topical report BAW-10103A, Rev. 3.

The B&W evaluation resulted in certain recommended operating moces:

Mode A - establish a gravity flow from the decay heat drop line through the LPI string not in operation to the reacter building emergency sump. If this is not possicle because the cecay heat drop line is routed above the hot leg nozzle, the drop line will be aligned to allow part of the LPI injection to

_. __ flow backward through the drop line into the hot leg. (This corresponds to Mode 2 of BAW 10103A, Rev. 3)

Mode B - hot leg injection using the Decay Heat system. (This corresponds to Moce 3 of BAW 10103A, Rev. 3.)

Depending on the decay heat pump operating, implementing Moce A cr B

'would recuire cperation of the decay heat cross connect (DH-V35 A/2),

throttling the DH-Vl9 A/B valves, cpening DH-V64 and RC-V4 anc cicsing RC-V3, or opening either DH-V12 A or B as well as DH-V1, V2, anc V3.

t Post-accident radiations levels restrict lccal manual operation cf some of these valves. To assure operability of those valves, wnicn recuireo local operation, air or motor operators or, in the case of DH-V64, reacn rods were planned to permit remote operaticn.

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'II. System Functional Recuirement Baron precipitation must be prevented to assure aceouate long term core cooling. Figure 10-4, extracted frcm BAW 10103A, Rev. 3 shows the builoup curve for boron as a function of time. Tne turnaround peint fcr concentration is dependent on the time at whicn forced circulation can be provided. With hot leg injection two effects occur:

1.- The time of effectiveness is cepencent on flow rate since the steaming must be overcome and,

2. The approach to equilibrium is affectec by the injection rate.

Two curves for hot leg injection are shown.

The highest concentration shown corresponcs to an estimated flow of 40 gpm and is adequate to prevent baron precipitation. Note that an extremely long time (1000 hrs) is availacle to establish this injection path. Based on the above, the functional requirement for baron precipation prevention can be stated:

1. Establish a forced circulation letdown path (Mode A), cg;
2. Provide greater than 40 gpm injectec into the RCS hot leg within approximately 1000 hours0.0116 days <br />0.278 hours <br />0.00165 weeks <br />3.805e-4 months <br /> (i.e. Mode B).

Since this is a required accident response function, the method (cr combination of methods) used must be single failure proof. Tne modification proposed below together with existing features provices redunoant means of implementing item 2 abcve (i.e., hot leg injection greater than 40 gpm).

III. Procosed Modification GPUN proposes that, in lieu of remote opertors on DH-Vl9A/S, DH-V12A/S, and DH-V38A/B, a cross connect be acced to the Decay Heat System which would essentially provide a second method of implementing Mode B (the first method is via DH-V64 and RC-V4 using existing remote operators).

Implementing mode A would tr.en be unnecessary.

Figure i snows the orcposed bypass line accification wnien provices an established path to prevent baron precipitation. Tne mocification consists of a 2 inch 304SS line of ac;roximately 100 feet in lengtn, socket welded with a 2 inch manual gicce valve. The new valve will nave a reach rod coerator installed in close prcximity to the snield wall cf the MCC 1 A & B wnere post accident access is consistent with the shielding study. The pipin; will be seisT.ically designec and suppcrted.

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IV. Evaluation Below is a list of advantages for the newly prep 0 sed modification over the previously planned approach to provice personnel access for post accident baron precipitation control.

1. Both approaches satisfy the functional recuirements ano are sincle ~

f ailure proof. Both use methods which are witnin the b0unds ef the B&W topical report.

2. The bypass line provides a more positive nechanism for contrclling boron precipitation i.e., injection rather than letoown.
3. Because of the larger magnitude of work required to install the remote valve operators, the bypass line can be installed in a more timely manner at lower cost (Table 1).
4. The potential for operator error in implenenting a boren control flow path is much less using the proposeo bypass.
5. The potential for spurious operation of DHRS valves (e.g. curing fires) is lower.

Conclusion Either the remote valve operators or the bypass line arrangement will provice

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the required boron precipitation control based on the analysis presentec in the B&W topical report. The conceptual designs will tolerate a single failure. The system.will not interfere with prcviding other essential pcst-accident mitigation functions. Therefore, it is concluced that tne proposed approach is technically acceptable. Scheculer and other improvements make the bypass line modification preferrable.

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Figure 10-4. Iloron Concentration Vs Time 100 o

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