ML20083J405
| ML20083J405 | |
| Person / Time | |
|---|---|
| Site: | Crane |
| Issue date: | 01/05/1984 |
| From: | Zahler R METROPOLITAN EDISON CO., SHAW, PITTMAN, POTTS & TROWBRIDGE |
| To: | Chilk S NRC OFFICE OF THE SECRETARY (SECY) |
| References | |
| NUDOCS 8401100139 | |
| Download: ML20083J405 (9) | |
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- anot Acmertts p.es O C W4tTEm 5 OsaECT D'AL NwMBE R (202) 822-1130 January 5, 1984 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. 50-299 (Restart)
Dear Mr. Chilk:
On November 4 and December 19, 1983, the NRC. Staff provided information to the Commission licensing and appeal boards, and' parties to the TMI-l Restart proceeding relating to krypton-85 leakage paths between TMI Unit l-and Unit 2.
See Board Notifica-tion BN-83-177'and BN-83-190.
Enclosed is a December 22, 1983 let-ter (5211-83-360) from H.
D.
Hukill, GPU Nuclear, to R.
W.
Starostecki, NRC, bearing on the same subject.
Respectfully submitted, Robert E.
Zah er Counsel for
'censee cc:
Service List
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8401100139 840105 PDR ADOCK 05000289 Q
PDR g&'
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CNITED STATES CF AMERICA NUCLEAR REGL'LATCRY COHISSION BEFORE THE COMISSICN In the Matter of
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)
MerROPOLITAN EDISCN CmPANY
)
Docket No. 50-289
)
(Restart)
(Th:ee Mile Island Nuclear
)
Station, Unit No. 1)
)
SERVICE LIST Chairman Nunzio J. Palladino Dr. Reginald L. Gotchy U.S. Nuclear Regulatory Ccmnission Atanic Safety and Licensing Appeal Washington, D.C.
20$55 Boad U.S. Nuclear Regulatory Ccmrission Cannissioner Victor Gilinsky Washington, D.C.
20 55 U.S. Nuclear Regulatorf Ccmnission Washington, D.C.
20555 Ivan W. Smith, Esgaire CMman, Atanic Safety and Licensing Ccmnissioner Thcmas M. Ibberts Board U.S. Nuclear Regulatorf Camission U.S. Nuclear Regulatory Carission Washington, D.C.
20555 Washington, D.C.
20555 Ccmnissioner James K. Asselstine Shelden J. Wolfe, Alternate Cha1Iman U.S. Nuclear Regulatory Ccmnission Atmic Safety and Licensing Board Washington, D.C.
20555 U.S. Nuclear Peculatorf Ccmnission Washing:On, D.C.
20555 Cm missioner Frederick M. Bernthal U.S. Nuclear Regulator / Ccanission Mr. Gustave A. Linenberger, Jr.
Washingt.cn, D.C.
20555 Atmic Safety and Licensing Board U.S. Nuclear Peculator / Carlssion Docketing and Seriice Section Washington, D.C.
20555 office of the Secretarr U.S. Nuclear Regulatory Ccanission Richard J. Pzason, Escuire Washington, D.C.
20555 Office et Executive legal Director U.S. Nuclear Pegulatory Carission Garf J. Edles, Esqaire Washington, D.C.
20555 Chairman, Atcmic Safety and Licensing Appeal Board Jchn A. Levin, Esquire U.S. Nuclear Regulatory Cardssion Assistant Counsel Washington, D.C.
20555 Pernsylvania Public Utility Ommission P. O. Box 3265 Dr. John H. Buck Harrisburg, PA 17120 Atmic Safety and Licensing Appeal Board Marjorie M. Aanodt U.S. Nuclear Regulater/ Carission R. D. 5 Washington, D.C.
20555 Coatesville, PA 19320
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Douglas R. Blazey, Esquire Steven C. SPolly Chief Counsel Union of Concerned Scientists Depawt of Envircr: mental Resources 1346 Connecticut Avenue, N.W.,
41101 514 Executive House, P. O. Box 2357 Washington, D.C.
20036 Harrisburg, PA 17120 ANGRY /'IMI PIBC Ms. Icuise Bradford 1037 Maclay Street 2(I ALERT Harrisburg, PA 17103 1011 Green Street Harrisburg, PA 17102 Chauncey Kepford Judith H. Johnsrui Ellyn R. Weiss, Esquire Enviren:: ental Cohlition on Nuclear Eher Han:en & Weiss 433 orlardo Avenue 1725 Eye St., NW, Suite 506 State College, PA 16801 Washington, D.C.
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DCCKE7ED UW GPU Nuclear Corporation MUClear w J3-9 p1:19 l S',T47's$ufn#*
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TELEX 84 2386 00Q.;ii.; a iErr-Writer's Direct Dial Number:
- h A h CH December 22, 1983 5211-83-360 i
Mr. Richard W. Starostecki, Director Division of Project and Resident Programs U. S. Nuclear Regulatory Commission
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Regicn I 631 Park Avenue King of Prussia, PA 19406
Dear Sir:
Three Mile Island Nuclear Station, Unit 1 (TMI-1)
Operating License No. DPR-50 Docket No. 50-289 Inspection Report 83-30 The subject NRC Inspection Report (Section 6) reviewed the TMI-1/TMI-2 krypton release incident of August 29, 1983, and the licensees investigation and test to identify the release path.
The attached evaluation provides a detailed identification of verified and potential leak paths, as well as corrective action taken. This evaluation differs from that presented in Inspection Report 83-30.
We believe the attached evaluation to be more accurate of the two reports.
S cerely, "O
A i
H.
. Hukill Director, TMI-1 HDH: RAS:vj f Attachment cc:
R. Conte GPU Nuclear Corporation is a subsidiary of the General Public Utilities Corporation
y.
/ 'ACHMENT I e
On October 20, 1983, an investigation and test was conducted to determine
'the actual flowpath of the released krypton gas, the nature of any defi-ciencies in the environmental barrier, and recommendations for corrective action. -The sample and ventilation system conditions of August 29, 1983
-were duplicated for the. test. A tracer gas (R-12) was introduced at the same point as the krypton gas, and electronic leak detectors were used to identify the flowpath of the R-12. is a sketch of the test set-up.
The R-12 injection was initiated at 1758 hrs. The first detection of R-12 vapor occurred approximately 18 minutes later at the floor drain and clean out plug under the Intermediate Closed Cooling Surge Tank (IC-T-1) on the 348' elevation in the Spent Fuel Pool Area. R-12 vapor was also detected 3
at the floor drain just inside the entrance door to this area (both in the Unit 1/2' common air space). The next location where a flowpath was sus-pected was the entrance door to the Spent Fuel Pool Area and the elevator i
doors leading to this doorway (348el'.).
A-12 vapor was detected at this i
location at 1830 hrs. The personnel performing this test rode the elevator down to the 281' elevation, where R-12 vapor was heavily detected at 1842 hrs.
It is suspected that a drain line, that terminates after it penetrates the elevator shaf t just above the elevator sump at (-276' cl.), as well as the floor drain in the elevator equipment room is the cause of this leak.
Based on the test results, Plant Engineering concluded that when the krypton gas was injected into the Nuclear Sampling Room it travelled the path of least resistance into the drain system. The drain lines throughout the Auxiliary Building provided a path up to the Spent Fuel Pool Area at the floor drains directly below the Intermediate Closed Cooling Surge Tank (IC-T-1) and just inside the doorway to this area.
Due to the lack of a loop seal in these floor drains, a flowpath was created for the krypton gas.
In addition, i
the drain line at the bottom of the elevator shaft provided an additional flowpath for the krypton gas.
The airflow is drawn up the elevator shaft, where it can leak out around the elevator door seals and be drawn into the
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Spent Fuel Pool Area through the entrance door. These three (3) flowpaths
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allowed the krypton gas to disperse into the common air space (348' el. is common to both Unit 1 and 2) and be exhausted by both units' air handling systemswhich caused the alarms in both units.
It should be noted that it took ~20 minutes from the time of injection for the krypton gas to produce a Fuel Handling Building radiation monitor alarm in the Control Room.
This is consistent with the approximate 18 minute time t
frame to detect the R-12 vapor at the 348' elevation of the Fuel Handling Building, during this test.
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i L
G All of the verified leak paths appear to be due to the lack of drain system loop seals and door seals. Job tickets have been initigted to correct verified leak paths (see items 1, 2, 3 and 4).
Loop seals were promptly re-established in the leaking floor drains and all appropriate floor drain loop seals were identified for inclusion in surveillance and' maintenance procedures. Loors to the Spent Fuel Pool area (348' el.) and shipping and receiving area (305' el.)
of the Fuel Handling Building have been made air tight.
The drain line at the bottom of the elevator shaft (276' el.) will be permanently capped. Actions have also been completed to minimize any potential (See Items 5, 6, & 7 attached) leak paths between the Auxiliary and Fuel Handling Buildings.
The above test and corrective actions have elminated both verified and potential pathways for gross air exchange between units.
It is not believed that further testing is necessary.
Also, the design of the environmental barrier and separation of ventilation systems has been reviewed, and following completion of the corrective actions no further changes are deemed necessary.
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u'g ATTACHMENT 2 - CORRECTIVE ACTION LIST The following is a list of company identified items and corrective actions.
Item 1 Auxiliary and Fuel Handling Building Drain System
. The R-12 test results clearly establish drain system problems.
Many of the floor drain loop seals are not maintained and some are not included in the Operation Surveillance Procedure (OPS-S59) or in Utility PM U-17 to_ clean all Zurn check valves.
Procedure changes are being generated identifying all the drain valves for inclusion in OPS-S59 and PM U-17 checklists.
Item 2 Entrance door to Spent Fuel Pool Area (348' elevation).
The door should be air tight.
Install new door lock and door knob.
Install new rubber door seal at the bottom of door. The door should be turned around to allow the door to seal against the door frame.
i JT #CC435 was initiated to correct this problem.
Door knob penetration is sealed.
Doorknob is on order. The door was rehung and new seals installed.
Item 3_
Personnel door for entrance to Shipping and Receiving Area (305' elevation) of Fuel Handling Building.
'The door should be air tight.
Fill the two (2) inch hole in. door-by installing a cover on both sides of door.
Install new door knob and latch.
Install new rubber door seals at the bottom of door and around door frame.
JT-#CC383 initiated.to correct this problem is complete.
Item 4 Drain line at bottom of elevator shaft.
Fuel Handling Building (276' elevation).
Repair drain line that penetrates into bottom of elevator shaf t.
Drain line should be capped.
If possible, braze cap on to drain line to prevent loosening of' cap from vibrations.
y JT #CC384 has been initiated to correct this problem.
Item 5 Opening under Intermediate Cooling Surge Tank, 348' elevation in l
Spent Fuel Pool Area.
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Opening for penetration to Surge Tank should be sealed with fire barrier penetration sealant.
This opening provides a potential flowpath from the 329' elevation to the Spent Fuel Fool Area (348' el.)
JT #CC385 initiated to correct this problem is complete.
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o Item 6 Decay Heat Closed Surge Tank Toom, 329' el'evation of Fuel Handling Building.
There are 3everal open penetrations in the wall of this room leading into the Fuel Handling Building ventilation chase. The chase is open down to the 281' elevation of the Auxiliary Building. Fill openings with fire barrier penetration' sealant.
JT #CC386 initiated to correct this problem is complete.
Item 7 Environmental Barrier Roof Decking, 351' elevation of the Spent Fuel Pool Area.
Gaps in the sheet metal seam must be filled.
Use RTV sealant.
JT #CC382 initiated to correct this problem is complete.,
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