ML20004E166

Forwards Hd Hukill 810526 Ltr to Jf Stolz W/B&W 810526 Ltr on Reactor Coolant Pump Suction Small Break Loca.Licensee Will Not Modify Any Guidelines Re Small Break Loca.Ltr Might Have Bearing on Issues in Hearing.Certificate of Svc Encl

ML20004E166
Person / Time
Site:	Three Mile Island
Issue date:	06/04/1981
From:	Baxter T METROPOLITAN EDISON CO., SHAW, PITTMAN, POTTS & TROWBRIDGE
To:	Jordan W, Little L, Smith I Atomic Safety and Licensing Board Panel
References
NUDOCS 8106110288
Download: ML20004E166 (2)

Text

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SH AW. PITTMAN, PoTTs & TROWBRIDG E 1800 M STR E" ET. N. W.

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- -AmCi A m. NmCNsTColsoM JyQlTM A. sANQLCm '" June 4, 1981 no Enf S. aceSINs Ivan W. Smith, Esquire Dr. Walter H. Jordan Chairman Atomic Safety and Licensing Atomic Safety and Licensing Board Board Panel U.S. Nuclear Regulatory Commission 881 West Outer Drive Washington, D.C. 20555 Oak Ridge, Tennessee 37830 Dr. Linda W. Little Atomic Safety and Licensing Board Panel 5000 Hermitage Drive

(

Raleigh, North Carolina 27612 i

In the Matter of Metropolitan Edison Company (Three Mile Island Nuclear Station, Unit No. 1)

Docket No. 50-289 (Restart)

Administrative Judges Smith, Jordan and Little:

l Please find enclosed a letter dated March 25, 1981, from Babcock & Wilcox to GPU Service Corporation on the subject

" Reactor Coolant Pump Suction Small Break LOCA," and a letter i

dated May 26, 1981 (LIL 159) which transmits the B&W letter l from Metropolitan Edison company to the NRC Staff.

l While the B&W letter has been evaluated and does

- not cause Licensee to modify any of the operator guidelines or system actions that had resulted fr;m previous small-break Q 8186 u og S$ i l A

, , , + +-v y ,- w w - - - - - p w - ---

SHAW, PITTMAN, POTTS & TROWBRIDGE Ivan W. Smith, Esquire Dr. Walter H. Jordan Dr. Linda W. Little June 4, 1981 Page Two LOCA analyses, Licensee transmitted the B&W letter to the NRC Staff and s hereby filing it with the Board and the parties because it might be considered to have some bearing on the issues in the restart hearing.

Licensee's witnesses on the subject Additional LOCA Analysis (Board Question UCS-8) 'have reviewed the B&W letter and determined that the letter does not warrant any change to their testimony previously given at the hearing.

Respectfully submitted,

- w Thomas A. Baxter Counsel for Licensee TAB:jah Enclosures cc: per Certificate of Service

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Metropolitan Edison Company

'f(') " Post Office Box 480 Macdletown, Pennsylvania 17C57 wnter's Direct Dies Numoer May 26,1981 L1L 159 Office of Nuclear Reactor Regulation A::n: John 7. Stol:, Chief Operating Reactors 3 ranch No. 4 U. 5. Nuclear Regulatory Coc=ission Washing on, D.C. 20555

Dear Sir:

Three Mile Island Nuclear Sta:icn, i;ci: 1 (U.I-1)

Operating License No. DPR-50 Docket No. 50-289 Small 3reak LOCA The e$ closed letter was provided :o GPU by 35W for censideration in conjunction with ongoing ac:ivi:1es associated vi:h small break I,0CA analysis. I: is provided here for your info =ation. We have reviewed :his le::er against analysis previously developed for :he dete=ina: ion of system perfornance para =eters to mee: Appendix K to 10CyR50 and against analysis developed since :he MI-2 acciden:

which define an expanded basis for opecator guidelines. We have concluded tha:

the info mation contained in this let,ter would not cause us :o alter any previous conclusions with respec: to cocpliance wi:h Appendix I 'or =odify any of :he operator guidelines or sys:e= actions that had resul:ed frc= previous analysis.

We have, as suggested by 36W, confi=ed tha: our plans to upgrade the ti=eliness and availabili:y of emergency feedwater vill ensure EF",i flow within one =inute of an ac:uation signal. Further, the ac:ua: ion signals vill also be upgraded consistent vi:h guidance based on earlier analyses. See enclosure 3 :o Licensee le :eridated January 23, 1981 (TLL 680).

Sincerely,

~)/ /

.2 . D. ukill Director, IMI-1 EDE:CWS:1=a Enclosure cc: D. Dilanni H. Silver L. 3arre::

Me:rc:cli:3n 6sen Ccrn any :s a t. tem:er of :ne Generar Fh;;h: U:::4nes Sys:em

i Nudeer Power Genershon oMston 8abCOCk & WilCOX a Mcoermott comcany 3315 old Forest Acac P.C. Sox 12M March 25. 1981 LYa:"8u' V"s'a'a 245cs

1. 38'5"'

File- 177/T1.2 ESC-63:

GPU-81-042 Mr. D. G. Slear TMI-l Project Engineering Manager GPU Service Corcoration .

100 Interpace Parkway ,

Parsippany. New Jersey 07054

Reference:

R. W Ganthner to D. G. Slear letter of October 3. 1980

Subject:

-- Reactor Coolant Pump Suetion Small Break LOCA

Dear Mr. Slear:

Following the TMI-2 accident, the NPS requested several small break accident scenarios be evaluated in order to develoc operator guidelines for

%hese events. These an,alyses included scenarios wnere auxiliary feedwater (AFW) was assumed not to ce available at the start of the event. The assumec worst case small break LOCA (less than 0.01 f t.2) for these analyses is recat'ed at the reactor coolant pump discharce. This assumption was made because under normal circumstances a greater degree of HDI penetration into the reactor vessel

.is achieved during a sue. tion line break. The purpose of this let.ter is to provide some information regarding this worst case assumptionAas it is affected brief summary in the scenario where HPI is not actuated and AFW is delayed.

of this situation was provided to you in the referenced letter. Specific details are included in this letter.

For pump suction line breaks, under normal circumstances, :00% of the HPI-flow enters the reactor vessel. For,However, pump oischarge line breaks only about 70%

for the scenario w1ere break si:e of the HPI. flow enters the versel.

is such that HPI is not automatically initiated and AFW flow is delayed. the-rate of system inventory loss before AFW actuation becc=es important. During pump discharge breaks a two phase discharge results due to the eff 2ct of the reactor vessel internal vent valves. This reduces the rate of system inventory loss. A pumo suction break will result in the loss of lower quality fluid which will deplete system inventary at a higher rate. Thus at the time of AFW actuation the RCS inventory will be less for the pump suction line break than for the pump discharge line break. e . u.

n..c.- - -.. .)

G?DSI2/:Ic;-).

APR 2 EEC'O

Analyses which have been conducted for the pump discharce break condition demonstrate that coerator actions to start AFW flow in 20 minutes will .sult in acceptable conditions. However. for the case where there is a pump suction

~

break of a size 'such that boil dry of the stesn generators occurs prior to an RCS pressure decrease to the HPI actuation setooint, the 20 minute delay in AFW actuation has not been demonstrated to result in an acceptable RCS inventory condition. That is the 20 minutes of delay analyzed for in the cump discharce break case has not been analyzed for in the pumo suction break case. Thus.

although there is certainly a delay in AFW actuation which will result in acceptable conditions, the actual time has not been identified for the pump

• suction break condition. ,

While the actual analyses for the pumo suction break celayed AFW scenario has not been conducted, there is a significant amount of guidance for the operator regarding actuation of HPI and AFW. Followine the TMI-2 accident, small break LOCA operating guidelines were develooed. These guidelines instruct the operator to ensure that AFW is being delivere: to the steam generators and if it is not, to restore feedwater as soon as posiible. Additionally the guidelines reccire manual actuation of HPI shoulc the system reacn saturated conditions. These actions crovide for mitigation of the celayed AFW scenario.

Additionally, uogrades of the AFW control system have been imolemented wnich would ensure AFW flow in times on the ordgr of one minute. Thus. althouch the

- specif.ic analysis has not been conducted. there is adecuate reason to believe that current procedures ,and system characteristics make the identification of 2 ""

the specific ti=e delay superfluous. However. It is not clear wnat significance the demonstration of a 20 minute ocerator response time was to the NRC. The licensing significance associated with the demonstration of a 20 minute operator response time is best determined by each utility. Additionally, the AFW upgrades are plant dependent and S&W cannot assess to what extent the probability of this event has been diminished. At present, the following positions appear to be possible resolution paths on this issue: .

1. Review the AFW systems and confirm that the small break LOCA with

~

delayed feedwater is a highly unlikely scenario and need not be considered part of the design basis for the plant. Thus, while the analyses performed may not have considered the worst break location for demonstrating the minimum allowable coerator response time. the probability of this event along with the generation of the operator guidelines provide adequate assurance that this transient can be safely mitigated.

2. Use the basic position outlined in Item 1 except report to the Commission the poten;ial change in the previously suomitted analyses.

3. Perform detailed evaluations of the pumo suction small break LOCA with a delay in the delivery of AFW and determine the time frame available to the cperator to restore either feedwater or HPI.

3-It is S&W's position that Item 3 is not necessary. We believe that either Items 1 or 2 are viable alternatives for the ultimate resolution of this issue.

If you have any questions regarding the nature of this concern. please call me (804-384-5111. extension 3489) or R. W. Ganthner (804-334-5111. extension 2751) at our Lynchburg office. .

Very truly yours.

, /

]ff' S. H. Duerson Engineering Product Manager

_. cc: J. G. Herbein -

~

R. A. Knief ' .'

E. G. Wallace J. J. Colit:

R. J. Toole -

J. F. Frit:en D. W. Demers ,

R. W. Keaten

._ ;, H. D. Hukill  :.

F. R. Faist K. Menon

. L. R. Allen ,

O G

e

UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION BEFORE THE ATOMIC SAFETY AND LICENSING BOARD In the Matter of )

)

METROPOLITAN EDISON CCMPANY ) Docket No. 50-289

) (Restart)

(Three Mile Island Nuclear )

Station, Unit No. 1) )

CERTIFICATE OF SERVICE I hereby certify that copies of the foregoing letter to the Atomic Safety and Licensing Board with attachments were served this 4th day of June, 1981, by deposit in the U.S.

mail, first class, postage prepaid, to the parties identified on the attached Service List. ,

'/W k. W Thomas A. Baxter

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

. v.,_.,

d UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION BEFORE THE ATOMIC SAFETY AND LICENSING BOARD In the Matter of )

)

METROPOLITAN EDISON COMPANY ) Docket No. 50-289

) (Restart)

(Three Mile Island Nuclear -)

Station, Unit No. 1) )

SERVICE LIST Ivan W. Smith, Esquire Jchn A. Iavin, Esquin Oahn Assistant Counsel Atcmic Safety and Licersing Pennsylvania Public Utility Ccmnission Board P.O. Box 3265 U.S. Nuclear Pegulatcry Ccanassicn Farrisburg, Penrsylvania 17120 Washington, D.C. 20555 Karin W. Carter, Esquin Dr. Walter H. Jordan Pcbert Adler,* Esquire Atcmic Safety and Licersing Assistant Attorney General Board Panel 505 Executive House 881 West Outer Drive P.O. Box 2357 Oak Ridge, Tennessee 37830 Harrisburg, Perr.sylmia 17120 Dr. Lirda W. Little Jchn E. Minnich Atcmic Safety and Licersing claican, Dauphin Cbunty Board Board Fonel of Ccrmissiorars 5000 Hennitage Drive Dauphin County Courthouse Paleigh, North Carolina 27612 Front and Market Streets Harrisburg, Perr.sylvania 17101 James R. Tourtellotte, Esquire Office of the Executive Iagal Director Walter W. Cohen, Esquire U.S. Nuclear Pegulatory Cccmission Censuner Mvocate Washington, D.C. 20555 office of Corsumer Mvocate 1425 Strawberr/ Square -

Docketing and Service Section Harrisburg, Pennsylvania 17127 Office of the Secretary U.S. Nuclear Pegulatorf Comrdssicn Washington, D.C.. 20555 i

Jordan D. Cunningham, Esquire Ecbert Q. Pollard 2320 North Second Stmet 609 htntpelier Street Feisburg, Pennsylvania 17110 Baltinere, Maryland 21218 Ms. Icuise Bradford Chauncey Kepford

'IMI ALERI' Judith H. Jchrsrud 315 Peffer Street Environmental Coalition en Nuclear Powr Earrisburg, Penztsylvania 17102 433 Orlando Avenue State College, Pennsylt mia 16801 Ellyn R. Weiss, Esquire Hanicn & Weiss Shiin I. Iawls 1725 Eye Street, N.W., Suite 506 6504 Bradford Terrace Washington, D.C. 20006 Philadelphia, Pew sylvania 19149 Marjorie M. Am:cdt Steven C. Shelly

. Unicn of Concerned Scientists R. D. 5 1725 Eye Street, N.W., Suite 601 Coatesville, Pennsyhwtia 19320 Washingten, D.C. 20006

'Ihema J. Germine, Esquire Gail Bradford Deputy AttcIney General ANGRY Divisien of Law - Pccm 316 245 West Philadelphia Street 1100 Faymond Boulevard Yor'<, Pennsylvania 17404 Newark, Nea Jersey 07102

. William S. Jordan, III, Escuire '

Haracn & Weiss -

1725 Eye Street, N.W., Suite 506 Washington, D.C. 20006 t

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