ML20101A990
| ML20101A990 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 12/14/1984 |
| From: | Bradford L THREE MILE ISLAND ALERT |
| To: | |
| Shared Package | |
| ML20101A988 | List: |
| References | |
| OLA, NUDOCS 8412200007 | |
| Download: ML20101A990 (10) | |
Text
gy DOCKETED UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSIOtl14 EC 13 N0:17 Before the Atomic Safety and Licensing Appeggpppy BRANCH In the Matter of -
))-
METROPOLITAN EDISON COMPANY.'
) Docket No. 50-289 OLA
)'
(Three Mile' Island Nuclear -
) (Steam Generator Repair)
Station, -Unit No.1)-
)
MOTION TO REOPEN THE RECORD ON Tile BASIS OF NEVI INFORMATION For the reasons described in the accompanying Brief on Appeal from Initial Decision in Steam Generator Repair, TMIA hereby moves the App. cal Board to reopen the record on TMI-1 Steam Generator Repair, to receive into evidence new information which has recently become available to TMIA.
The significance of this new information is adequately explained in the accompanyincj Brief on Appeal from initial Decision in Steam Generator Repair.
See in particular, pp. 8-11.
This information was submitted to TMIA in the course of discovery on the reopened hearings on training issues. Attachment 6 was recently made available to the Board and parties by counsel for Licensee.,
The new information is of safety significance and might have dictated.a different result had it been part of the record.
Respectfully submitted, g2 gogo Nhd CF' o
DR C
Louise Bradford v
e k
O MGk & v.W L
/-
PERSONAL AND CONFIDENTLE Intor-Gifico Memorandum
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vate "
October 19, 1983 '
p File:! Weekly Fcport/ Sign. Events Subject.
TMI-l PIANT STA'IUS REPORT EOR THEi PERIOD SEPIDIBER 30 - OCIOBER 14, 1983.o Report-3000-83-321' '
To N R. C. Arnold - President.
Location u 'IMI - Trailer #122 P. R. Clark-4 Executive Vice President The plant status report for the subject period'is indicated belm:
PIAVf STATUS The~ plant is presently cooled dwn with a steam bubble in'the pressurizer.'
Temperature is being mintained at 130 F + 100 F and pressure at 320 psi.
Pressurizer level is being mintained at 100 - 150 inches. At the request of Technical Functions, one main coolant pump is in service to ensure
/
circulation in the primry plant. Both steam generators are in full, wet layup.
1 Hot steam generator testing, which comenced on August 27, was ccupleted successfully and the plant cooled dwn-6n October 6.
The initial testing sequence called for three cooldwns. Hwever, because of the need to obtain a tube-to-shell A T of at least 700 F, a forth cooldown was conducted using emergency fee 64ater vice min feedsater and a~ cooldwn rate of 90.F/ hour. On the 'other cooldwns, the maximum tube-to-shell A T obtained 0
F/ hour..During the special coold wn using emergency feed-was about 460 water, we were able to obtain a AT of about 1100 F.
The initial evaluation by Technical Functions of the results of the steam generator testing are i
very encouraging. Icak rate frm the initial results is approximately one gallon per hour + 50%. The raw data frcm the test program is still under evaluation, and a report is being prepared for subnittal to the NBC.
During and subsequent to the final cooldwn, it was noted that sulphates increased and approached their limit of 100 ppb in both primary systan and.
on the secondary side of the steam generators. Neither the plant nor Technical Functions are absolutely sure of the reason for this. It could be problems with the am onium hydroxide addition,' interference in the sampling process because of amonium hydroxide,'or, in fact, sulphates still being released from the surfaces within the systen. To alleviate-
-the problem, we drained and refilled both steam generators and used an.
anion bed demineralizer for the primary systan. Prirary sulphates are now in the'30 ppb region, but steam generator secondary sulphates are still indicating high.. This problem is being investigated.
Surprisingly few material problems were encountered during the cooldwn, and the performance of the operators was basically superior to that A0000640 6
nwe.eu zc I-PERSCNAI. AND CCNFIDWTIAI, Intor Office Memorandum
, de November 30,~ 1983 y +]
f
'IMI-l PIANT STATUS REPORT IDR THE,
a s
Subject PERIOD NOVEMBER 12,1983 '111POUG ^
File
. Weekly Peport/ Sign.
NOVEMBER 25, 1983' Events Report
'3000-83-356.
To m P.iR. Clark - President Location ' t 'IMI - Trailer #122 ?
E.: E. Kintner.- Executive Vice President a f
The plant status report for the subject period is indicated below:
PIRIP STA'ItJS Installation of the taps for the water level trending instrumentation and the head vents were empleted. The primry system has been refilled, 0
and at the direction of Technical Functions, we are mintaining plant pressure at 312 psig, with a steam bubble in the pressurizer and tmpera-ture at 120-1300 F.
The min coolant pump will be run continuously with the decay heat system in operation to mintain temperature. We plan to further consult with Technical Functions on the necessity to mintain-a coolant pump running at all' times. : If this is not necessary to ensure proper primry plant chanistry conditions, it will be our g
reconmendation to periodically run a punp rather than run one continuously.
When refilling the primry systan, sulphates and chlorides showed a definite. increasing trend. This phencmenon has been noted on each occasion that we have been required to refill the system fran a drained condition. : We are unable to explain this situation and are working with Technical functions to determine the exact cause. We have since cleaned up the primary system, and both chlorides and sulphates have been reduced well below specification.
on checking the installation of the head vent connection, it was determined that the connection was mde to the wrong blank flange on the head. 'Ihe reason for this error in installation is still being investigated. This problan presents us with two alternatives: either drain down again and connect the head vent tap to the correct flange, or redo the engineering for the remainder of the head vent installation to acm Aata the present connection.: I have requested that Technical Functions review the ramifications of redoing the engineering to fit-the present configuration. My initial reaction-is that this will require considerable rework,' time and effort, and in" the long run, it will'be sinpler to drain down and redo the connection. There are eight similar.
blank flanges on the head which could be used for this installation, and the tie-in to any one of them is very sinple. Therefore, the A0000648
l CONF.IDENTIAL 3
[r 0 ] Nuclear Memorandum
Subject:
IMI-l PIANT STATUS REPORf FOR TEE PERIOD Date: August 28, 1984 AUGUST 11, 1984 THRU AUGJST 24, 1984 From:
H. D. Hukill - -
Location:
IMI - Trailer #122 "
Vice President & Director, TNI-l File: Weekly Significant Events Reports To:
P. R. Clark - President 3000-84-302 The plant status for the subject period is indicated below:
PIANT STATUS The BCS is in cold shutdown, with tenperature at approximately F, and the system depressurized and drained to 10-15 inches
-1100 above the center lines of the cold legs. The upper and lower y
nunways on the steam generators are removed for investigation and further corrective action for the steam generator plugging problan as described below.
During this period, the pull testing of the Westinghouse mechanical I
plugs was conpleted with the folicwing results:
1,006 Plugs Tested 728 Passed 253 M)ved Slightly, then Stopped 25 Came Out The above figures do not ih::lude the 6 plugs that were found missing-1 in the lower heads of the steam generators (4 "A" - 2 "B") and are assumed to be in the vessel. The above failures also do not include-the one plug that came out in the upper "A" and found its way into another tube, and one plug that was missed in the. test program and l
will be picked up later.
A meeting was held on site with senior representatives from Westinghouse, the Plant Staff, and Technical Functions to establish the cause for the plug failures and to set plans and schedule for necessary repairs..
It was agreed by all in attendance that the probable cause of the loose plugs was an installation problem and that revised specifications and tooling should correct this problem. It was also agreed that the 728 tubes that passed the pull test are satisfactory as installed and will not be worked. The 253 plugs that noved slightly and then stopped will-be rerolled using a modified tool and nore stringent specifications,-
These l
including detailed training of the individuals doing the work.
j tubes will be pull tested after rerolling. Plant Staff personnel will be assigned to do this work. The plugs that came out will be replaced I
' A0000648 8 03 l
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PEPSONAL MiD CONFmWIIAI.
Intor Offico Memorandum S
rAjggwM@U@ST
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Date '
Jantiary 4,1994
~
Subject
'IMI-l PIANT STATUS REPORT FOR ' DIE File Weekly Significant Events Peport PERIOD DECEMBER 10, 1983 Tm OUGI-
.3000-84-003 DECSEER 30, 1983 Location -
TMI - Trailer #122 To' P. R. Clark.- President:
E. E. Kintner - Executive Vice President The plant status report for the subject period is indicated belcw:
PIRIT STA'IUS In my last report I indicated that the primry system was partially drained to permit reinstallation of the head vent connection to the correct flange on the head and to permit work on approximately 30 valves in the mkeup system. This work was ccepleted during the week of December 12, at which time the primary system was refilled, a bubble g
drawn and a main coolant pump run continuously, in conjunction with the decay heat system. Primary pressure is being mintained at 310 psig, with ter:perature at 120-1300 F.-
For about a, week during this period, the main coolant pu::p was secured and pressure reduced below 100* psig to permit valve maintenance.
The secondary plant has been returned to the full wet layup condition follcwing partial drain acun for mintenance on valve and steam line After refilling, the sulphate concentrations increased in supports.-
both generators to greater than 200 ppb. Facent history has demonstrated that al::ost any changes in secondary side water level or chemistry conditions result in an increase in sulphate concentratiory, which gradually reduces to normal values (20-100 ppb) in a matter of days. The same phenmena has been noted on the primary side, however, chlorides also increase with sulphates. On the primary side we put a demineralizer in service to reduce both' chlorides and sulphates. We are working with Technical Functions in an attempt to determine the cause and preventive /
corrective actions for this problem.
Baron crust was noted on scme studs for two 1cuer and one upper steam The studs were cleaned, and two studs were generator manway covers.
removed and inspected by QC satisfactorily. All~ bolts have been removed, cleaned and reinstalled with a higher torque value approved by Technical.
Functions.
Tube plugging was completed on feedwater heater 8B. Plugging remains to be ccr:pleted on three feedwater heaters.
A0000648
pl Lu uJ 5
PERSONAL AND CONFIDENTIAL
}
Inter-Office Momorandum Date.
January 17, 1984 g---m 3-;
TMI-l PIANT STATUS FEPORI' EOR 'IEE '
b dul d {' Q' QA ][.
4"'
f J
"b Subject. PERI D
ER 31,1983 UIPOUGH File: Weekly Significant Events Peport 3000-04-024*
To "
P. R.iClark - President Location - VII - Trailer #122 The plant status report for the subject period is irdicated belw:
Plant Status
- The BCS is in a cold shutdwn condition with a decay heat pump and main coolant pump operating. There is a bubble in the pressurizer, with pressure being mintained at about 310 psi and temperature at about 1300 F. -The secondary side is in partial wet layup (steam lines drained). A vacuum has been drawn on the secondary side, and the plant is basically ready to comence heatup for hot functional testing.. It would take about two days to heat feedaater and get in specs prior to concencing the heatup.
i
- During this period, feodaater was heated tip and brought into chemistry specs to conduct the emergency feedaater flw test. The emergency feed-water flow test was conducted satisfactorily and the new flw indicators worked properly.
- The steam generators were drained and refilled on several occasions to maintain sulphates within specification.
- Icaking tubes were plugged in feedwater heaters 2A, 2B and 4B. All feed-water heater work has been conpleted and heaters returned to service.
- Building spray pump 1B was reassembled and returned to service.
- The overhaul and reassembly of condensate ptmp 1A was cccpleted, and the-ptmp returned to service.
- The third internal Festart Peadiness Paview Ccmittee meeting was conducted on site on January 12. At this meeting all remaining open items were-presented to the Comittee. The Ccmittee granted permission to proceed -
with Flag 2 (Hot Functional Testing 'and startup to 48%'pcNer) contingent upon the Unit 1 Director's certification in writing to the Ccmittee that all remaining open items are ccupleted and signed off. The Carmittee concluded that the plant will be ready to heatup the week of: January 16, and ready for critical operations about two weeks thereafter. This schedule A0000648 a
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--nm-- 4
- lJ GPU Nuct:ct Corporettose
?
g too triterpace Parkway y
g Parsippany,New Jersey 070541149 (201)263 6500 TELEX 136 482 Writer's Direct DialNurnber:
November 27. 1984 Shaw Pittman, Potts & Trowbridge Attn:
B. W. Churchill 1800 M. Street. NW Washington, DC 20555
Dear Mr. Churchill:
GPU Nuclear Corporation is currently performing the normal Technical Specification periodic eddy current inspect on ~of the TMI-1 steam generator tubes. Results from the initial 3% sample which are now available identify indications of potential defects in some tubes.
Characterization of these indications requires additional inspection and evaluation.
Most of the indications are in the "A" steam generator. They are predominantly low voltage ID signals of small circumferential extent.
Most indications are in the range of 40-60% through-wall,~and are located high in the steam generator, in peripheral tubes.
Identification of these indications is prompt reportable to the NRC staff based on Technical Specification 4.19. A telephone report was made to the resident inspector late on Friday, November 16. A written follow-up is required by December 17.
We will keep you informed of the results of the ongoing inspections and evaluations.
- cerely, Y he -
. F. Wi son Vice President Technical Functions dis:0869f GPU Nuctaar Corporation is a subs;oiary of General Pubhc ut.hties Corporat on J
S.';*t'f" ait G UNITED STATES OF AMERICA
- g g g g NUCLEAR REGULATORY COMMISSION L#;.i ; G..,,
00CriU 8% i !.EsV;U 3 RANCH
. Before the Automic Safety and Licensing Appeal Board In the Matter of
)
)
METROLOLITAN EDISON COMPANY
)
Docket No. 50-289 OIA
)
(Three Mile Island Nucicar
)
(Steam Generator Rapair)
Station, Unit No.1)
)
CERTIFICATE OF SERVICE I hereby certify that TMIA's "BRIEF ON APPEAL FROM INITIAL DECISION IN TMI-1 STEAM GENERATOR REPAIR OLA AND IN SUPPORT OF MCrfl0N TO REOPEN THE RECORD ON THE BASIS OF NEW INFORMATION" was served on the attached service list by deposit in the U. S. mail on 10 December 1984.
Louise Bradford Datedh December.14, 1984 9
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9 4
f e
UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION g. n.3
.:J:
Lefore the Atomic Safety and Licensing Appeal Board
'84 CEC 19 A10:57 In the Matter of
)
)
METROPOLITAN EDISON COMPANY, ~ET AL.
)
Dockh.....N6Ai$E259!.0LA
)
3 RANCH
~
(Three Mile Island Nuclear Station,,
)
3 Unit No. 1)
)
. SERVICE LIST Cary J. Edles Dr.' James C. Lamb, III Administrative Judge Administrative Judge l
Chairman, Atomic Safety and Atomic Safety and Licensing i
Licensing Appeal Board
' Board U.S. Nuclear Regulatory 313 Woodhaven Road i
Commission Chapel Hill, N.C.
27514 Washington, D.C.
20555 Mary E. Wagner, Esq.
' Dr."W. Reed Johnson
,0ffice of Executive Legal Direct Administrative Judge U.S. Nuclear Regulatory Atomic Safety and Licensing Commission Appeal Board Washington, D.C.
20555 U.S. Nuclear Regulatory Commission Atomic Safety and Licensing Washington, D.C.
20555 Appeal Board Panel U.S. Nuclear Regulatory Dr. Reginald L. Gotchy Commission Administrative Judge Washington, D.C.
20555 Atomic Safety and Licensing i
Appeal Board Atomic Safety and Licensing U.S. Nuclear Regulatory Board Panel Commission U.S. Nuclear Regulatory Washington, D.C.
20555 Commission Washington, D.C.
20555 Sheldon J. Wolfe Administrative Judge Docketing and Service Section ()
Chairman, Atomic Safety and Office of the Secretary.
I Licensing Board U.S. Nuclear Regulatory U.S. Nuclear Regulatory Commission i
Commission Washington, D.C.
20555 1
Wash,ington, D.C.
20555 Dr. David L. Netrick Bnre W. Churddll Administrative Judge Shar, Pittman, Potts & Trowbridge Atomic Safety and Licensing Board 1800 !! Street, N.W.
. College of Engineering Wadington, DC 20036 Dept. of Nuclear and Energy Engr.
j
.T,he University of Arizona Tucson, Arizona 85721
ASLAB SOrvica Lict Pcg3 Two
. TMI-l e
Thomas Y. Au Assistant Counsel i
Commonwealth of Pennsylvania Department.of Environmental Resources Bureau of Regulatory Counsel Room 505 Executive House P. O. Box 2357 Harrisburg, PA 17120 A
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