ML20070K654
| ML20070K654 | |
| Person / Time | |
|---|---|
| Site: | Crane |
| Issue date: | 12/29/1982 |
| From: | Trowbridge G METROPOLITAN EDISON CO. |
| To: | |
| References | |
| NUDOCS 8212300246 | |
| Download: ML20070K654 (4) | |
Text
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12/29/82 UNITED STATES OF AMERICA' NUCLEAR REGULATORY COMMISSION 003ETED t:StaC BEFORE THE COMMISSION T208: 29 P3:44 In the Matter of
)
7,, :, :
I,y METROPOLITAN EDISON COMPANY
)
Docket NoI"50-289
)
(Three Mile Island Nuclear
)
Station, Unit No. 1)
)
LICENSEE'S COMMENTS ON COMMISSION MEETING OF DECEMBER 17, 1982 At the Commission meeting on December 17, 1982, Licensee was afforded an opportunity to comment on the Livermore Technical Evaluation Report for TMI-l Seismic Qualification of Auxiliary Feedwater System and to summarize its commitments for upgrading of that system.
These comments and commitments have been confirmed in a letter dated December 20, 1982, from Mr. H.
D. Hukill, Direc-
'ar, TMI-1, to the NRC Staff.
A copy of that letter is enclosed.
Licensee has requested a meeting with the Staff and Livermore to expedite resolution of the EFW requirements.
Licensee plans no further comments on the matters discussed at the December 17 meet-ing.
Respectfully submitted,
/
AMn
. Asw' BIN MGeorgeF. Trowbridge, C.
Dated: December 29, 1982 8212300246 821229
^1 PDR ADOCK 05000289 0
GPU Nuclear Corporation r_!dihMUC[Sar PcSe"#Sct'S Eccisitwn.Pennsylvan:a 17057 7 5 7 C44-7621 TELEX 64-2386 Wnter's Direci Dial Number:
Dece:bar 20, 1982 5211-82-201 f
Office of Nuclear Reactor Regulation Attn:
J. F. Stolz, Chief Operating Reactor Branch No.' 4 Division of Licensing U. S. Nuclear Regulatory Co=ission Washingten, D.C.
20555
Dear Sir:
Three Mile Island Nuclear Staticn, Unit 1 (TMI-1) g Operating License No. DPR-50 Decket No. 50-289 Emergency Feedvater System - Seismic This letter is in response to the Technical Evaluatien~Lepert (TER) for DiI-l Seismic Qualification of Enargency Feedvater Syste= centained in your letter of Nove=ber 16, 1982. We have enclosed responses te the issues addressed in that TER.
As suggested in your letter, we have perforned a supplemental walkdo.n of the pertions of the EW system you have described as non-saistic.
The results are included in the enclosure.
In accordance with Genaric Letter 81-14 and our replies, we have not described an alternate decay heat renoval systs:. Lince it is cur pcsitien that with the:inor mcdification noted in our responses, at restart the existing E7W systen vill be able to perfor= its scfety function after the occurrenta of earthquakes up to and including the 55E.
Longer :cre upgrafes that are schaduled fer the first refueling after restart vill further si:plify the plant response to seismic events and reduce the potential for in,'lant fluid spills. Without regard to the foregoing, we note that as discussed in the December 14, 1981 ASLE Partial Initial Decision, E?I coolins tehich itses cnly safety grade ecuip-ment can servc as an alterntte decay, heat renoval system in the event both EFV and main feedwater systans are lost.
With cc pletion of the actions, addrerced in this letter and our previous letters on this subject, we have cc:rpleted our raview of the scisric capability of the
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1 C A/ W / w t~'O O jy GpU Nuciar C.c:ptrbonis ; 5 oc@.r, et 1% Se et::.t c. Urs C r Orcm
151. J. 7. Stolz 5211-E2-301 I
EW syste=.
Nevertheless, should you identify further questiens er deficiencies l
regarding the E W syste: please let us know prc=ptly, since it is our intentien to co=plete all identified long ter: =odificatiens tc the system 'cy ec=pletion of the next refueling outage.
Sdncerely,
)
l
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4.
D. Eukill irecter. TMI-1 HDS:EGW:vj f ec:
R. Jacobs 9
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eA e
IW TER C05'IICS' TIR Item 1 Piping (a) "The portion of the recirculation lines for the energency feedvater pt=p between manual isolation valves (EF-V 20 A/3 and IT-Y 22) and the cendensate storage tank (CST) "B" were not seismically designed."
Resnonse The flow through a failed recirculation line would not prescat a loss of safety function.
It would only create an inplant spill.
(See also TER ref. 7 Enclosure i 2).
Thus, completion of modifications during cycle 6 refueling is warranted.
TER Item 2 Piping (b) "...Hence the condenser horwell supply lines will be isolated when the water level of the condensate storage tank reaches the technical specification limit."
Response
The existing condensate storage tank level instrumentatien and alarm are not seismic but will be upgraded to safety grade during the Cycle 6 refueling outage.
The icvel signals for the low level and low low level alar =s are from the same transmitter which will be replaced by a qualified instrument.
At restart the operator will' isolate the EFW system by closing COV 111 A/B and COV-14 A/.5 whenever a tank reached the tech spec li=it following any EFW actuation; and during the interim period before the long term cods are complete, following any recognizable seis ic event.
TER ltem 3 Piping (c) " Based on the sketch submitted by the licensee, not all connected branch lines from the AFW Systa= are seismic class I beycnd the first valve and up to a point of three orthogonal restraints."
Response
A valkdoun of the branch lines has been performed and the cennection with the follcwing valves has been judged to be seismically adequate:
ETV-17 ITV-44 ETV-18 COV-27A/3 EFV-23 COV-12SA/3 ITT-24 COV-129A/E ITV-25 COV-130A/S ETV-26A/3 COV-131A/E EFV-27A/3 COV-132A/B, Is:1sted when COV-14A/3 shut by cperate E?V-28A/3 COV-133A/E - actica (See Response to Item 2).
ETV
'.9 COV-134A/E ETV-*2A/E EFW 3 earing Cooling Lines EFV-43A/B I
4 TEE lte:,_4 Piping (d) "The instru ent air supply line frco valve 11 ~l27 o the AFW syste:
is not seis=ically qualified."
Response
Although the instru=ent air supply line from valve :A-Y27 :c the EFW syste=
is not seismically qualified check valves qualified for SSE conditions are (i
provided to maintain the integrity of the Seis=ic Class I two hour air backup supply (bottled) for EFW 30 A/3; EFV 8 A, 3, C; MSV 6; a f MSV 4 A/3.
In accordance with figure 3 of our letter of July 7,1952, the following check valves are provided and qualified for SSE.
IAV 1433 IAV 1451 1AY 1445 1431 1645 1448 s
1655 1460 1446 l
1658 1458 1651 4
1656 1647 1636 1663 1643
'634 1437 1641 1649 1439 1455 1461
- l 1660 1457 1463 1661 1653 1637 1449 14(3 1639 1454 1452 1628 A/B TER Ite
- 5 Power Supplies a, b, c, "... we conclude that the present level of seis=ic capa-bility of power supplies is less than 03E, but it wil' be equivalent to SSE upen cc=pletion of the planned =odificatien."
Response
The f ailure of the power supplies noted will not prerent the EFk.' system free initially perfor=ing its safety function.
Adequa:e tire enists for
=anual actic to be taken to preserve ' '- - CS! dnvent:ry.
(see TER ref.
7).
The cc pletien of icng ter: =cds during Cycle i refuelin; ts warranted.
TIE Iran 6 Initiatien/Contrel Systers - Flow switches and cen ::'. circuitry tf recirtuistit:
flew centrol valves EFY S A, 3, and C."
Response
The recirculation flow control valves fail open en icss cf centrol signal.
This does not result in a loss of safety function (see resp::se to Ite: 1).
G?i'.; will upgrade the controls for the e=ersency feefvatcr pump recirculation valves EF-V-S A/3/C to safety grade and = edify the re:ir::'atien valve circuitry tt i=preve syste: cperation at lew flew conditicns.
1
TER Item 7 Initiation / Control Systems
" Cable routing to motor operators for cain steam cupply isolation valves to the turbine driven pump (MS-V-2 A&B) and for the main steam bypass to the condenser valves (MS-V-8 A&B).
Response
GPUN has evaluated the seismic portion of the el'actrical system associated with the emergency feedwater turbine driven pump.
In accordance with the cnalysis provided in the TMI-1 Restart Report 8.3.9 and TMI-1 FSAR 14.1.2.9, failure of the main steam isolation valves to close would result in a blow-down of both steam generators.
Such a transient can be sustained by the unit as described in the FSAR.
The high energy piping, valves and other mechanical components of the EFW turbine driven pu=p are required to be seismic to prevent seismically induced damage to the motor driven pumps.
Therefore, specific operation of these valves is not required to mitigate the consequences of a seismic event.
TER Item 8 Initiction/ Control Systems
" Solenoid valves and limit switch which control the valves (MS-V-13A and B) for providing the main steam to turbine."
p
Response
See Response to Item 7.
TER Item 9 Initine'.on/ Control Syste=s
" Cable routing of =otor operators for main steam isolacion valves MS-V1A, B, C & D."
Response
See Response to Item 7.
TER Item 10 Structures - The Turbine Building is seismic Class II and with some stiffening it would withstand OBE.
Response
The Turbine Building is a Class II building according to the building cedes not seismic Class II.
Nevertheless, the co=ponents associated with EFW system per-formance which are located in the Turbine Building ceuld fail without preventing the completion of the EFW safety function.
Therefore, the Turbine Building does not require seismic upgrading.
12/29/82 UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION BEFORE THE COMMISSION In the Matter of
)
)
METROPOLITAN EDISON COMPANY
)
Docket No. 50-289
)
(Tnree Mile Island Nuclear
)
Station, Unit No. 1)
)
CERTIFICATE OF SERVICE I hereby certify that copies of " Licensee's Comments on Commission Meeting of December 17, 1982," dated December 29, 1982, were served upon those persons on the attached Service List by deposit in the United States mail, postage prepaid, or as indicated by asterisk by personal service, this 29th day of December, 1982.
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Ge[rgeF.
rowbridge P.C.
Dated: December 29, 1982
UNITED STATES CF AMERICA NUCLEAR REGULAIOIE COMISSICN BEIORE 'IHE COMISSION In the Matter of
)
)
METIROPOLITAN EDISCN CCMPANY
)
Docket No. 50-289
)
(Restart)
('Ihree Mile Island Nuclear
)
Station, Unit No. 1)
)
SERVICE LIST
- Nunzio J. PallaAino, Chaiman Adminiptrative Jtidge Gary J. Edles U.S. Nuclear Regulatory Cmmiasion Chaiman, Atcmic Safety and Licensing Washingtcn, D.C.
20555 Appeal Boa.M U.S. Nuclear Teg'latory (Emission
- Victor Gilinsky, Cbmissioner Washington, D.C.
20555 U.S. Nuclear Regulatory emmi=sion Washington, D.C.
20555 Administrative Judge John H. Buck Atmic Safety and Li nsing Appeal Board
- John F. Ahearne, hinsioner U.S. Nuclear Regulatory emminsion U.S. Nuclear Regulatory Ocamtission Washington, D.C.
20555 Washingtcn, D.C.
20555 Administrative Judge Christine N. Kohl
- 'Ihcmas M. Ibh=rts, Ccmnissioner Atmic Safety and T.imnsing Appeal Board U.S. Nuclear Regulatory nminsion U.S. Nuclear Regulatory crmniasion Washington, D.C.
20555 Washington, D.C.
20555
- Janes K. Asselstine, Ocumtissioner Administrative Judge Inaginald L. Gotchy U.S. Nuclear Regulatory Ccmrission Atcmic Safety and Licensing Appeal Board Washington, D.C.
20555 U.S. Nuclear Regulatory o w iasion Washington, D.C.
20555 Administrative Judge Ivan W. Smith Chaiman, Atmic Safety ard Joseph Gray, Esquire (4)
Lioansing Board Office of the Executive Iegal Director U.S. Nuclear Regulatory n=insion U.S. Nuclear Regulatory remninsion Washingtcn, D.C.
20555 Washington, D.C.
20555 Administrative Judge Walter H. Jordan
- Docketing and Service Section (3)
Atcmic Safety and Licensing Board Office of the Secretary 881 West Outer Drive U.S. Nuclear Regulatory remnission Oak Ridge, Tennessee 37830 Washington, D.C.
20555 Administrative Judge Linda W. Little Atmic Safety and Licensing Appeal Board Atcmic Safety and Licensing Board Panel 5000 Hermitage Drive U.S. Nuclear Regulatory Ccmnissicn Raleigh, North Carolina 27612 Washington, D.C.
20555 l
Atcznic Safety and Licensing Board Panel Ellyn R. Weiss, h etire
-U.S. Nuclear Regulatory Cannission Harnum & Weiss Washingtm, D.C.
20555 1725 Eye Street, N.W., Suite 506 Washingtcm, D.C.
20006
)
Ibbert Adler hq' ire Karin W. Carter, hqiim Steven C. Sholly Assistant ALL.ua-sy General Union of Car-- M Scientists Otznanwealth of Pennsylvania 1346 Cuardcut Avenue, N.W. 41101 505 Ezecutive House Washington, D.C.
20036 P. O. BaK 2357 Barri=h rg, PA 17120 ANGRY /'JMI. PIRC i
.-1037 Maclay Street Assistant Counsel
~
] '.
John A. Isvin, Esquire
. Harrisburg, PA _17103 Pennsylvania Publi' Utility h iasion P. O. Box 3265 Mr. and Mrs. Norman Aamodt Harrisburg, PA 17120 R.D. 5 Coatesville, PA 19320 Jordan D. Cunningham, hq' ire Fox, Farr & Canningham Emica Bradford 2320 North Secmd Street
'IMI ALERP m vr4=h rg, PA 17110 1011 Green Street L
h rr4=h rg, PA 17102 L
W1114= S. Jordan, III, Esquire Harnon & Weiss Chauncey Kepford 1725 Eye Street, N.W., Suite 506 Judith J. Johnsrud Washingtcm, D.C.
20006 Envimmrnt.al Coalition cn Nuclear Power 433 Orlando Avenue State (.bilege, PA 16801 4
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