ML19329F992
| ML19329F992 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 07/02/1980 |
| From: | Herbein J METROPOLITAN EDISON CO. |
| To: | Grier B NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| References | |
| IEB-80-06, IEB-80-6, TLL-293, NUDOCS 8007110446 | |
| Download: ML19329F992 (4) | |
Text
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e Metropolitan Edison Company
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Middletown. Pennsylvania 17057
/17 044 4041 Writer's Direct 0.at Nurnber July 2, 1980 TLL 293 Office of Inspection and Enforcement Attn:
B.
H. Grier, Director U.
S. Nuc] car Regulatory Connaission Region 1 631 Park Avenue King of Prussia, Pa.
19406
Dear SLr:
Three Mile Island Nuclear Station, Unit I (TMI-1)
Operat ing License No. DPR-50 Docket No. 50-289 1C Bulletin 80-06 This let ter and at tachments are in response to your letter of March 13, 1980, forwa riling tE I ulleti.n 80-06 which concerned Engineered Sarc.ty Features Reset Controls.
Attached please find a response to items 1, 2, and 3 of the subject bulletin and letter of affirmation stating that the information herein is true and c.rrect to the best of my knowledge, information, and belief.
S i.n ce rely,
/s/ J. G. Herbein J. G. Herbein Vice President.
TMI-I JGH:DGM:1ma ALtachmentu cc:
J. T. Collins B. J. Snyder D. Dilanni H. Silver
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TLL 293 METROPOLITAN EDISON COMPANY JERSEY CENTRAL POWER AND LIGilT CO)1PANY AND PENNSYLVANIA El.ECTRIC COMPANY THREE MILE ISLAND NUCLEAR STATION, UNIT I Operating License No. DPR-50 Dc:ket No. 50-289 This letter is submitted in support of the Nuc1 car Regulatory Commission request concerning the March 13, 1980 letter transmitting IE Bulletin 80-06.
The responses to i t. ms 1, 2, and 3 of the subj ect letter are attached.
Further, all statemints contained in these responses have been reviewed and all such statments made and matters set forth therein are true and correct to the best of my knowledge, information and holief.
By
/s/ J. G. Herbein Vice President Sworn and subscribed to me this
/ day of 1980.
$I By Not Public CATHY L. BREY. Notary Puk loWoNetry Tws Deephen County Pa.
My Coeusassoon Espstes Oct. 24,1983 b
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o TLL 293 RESPONSE TO IE BULLETIN 80-06 ITEM 1:
Review the drawings for all systems serving safety related functions at the schematic level to determine shether or not, upon the reset of an ESF actuation signal, all associated safety related equipment remains in its emergency mode.
RESPONSE
The elementary diagrams for all ES actuated components at TMI-I were reviewed.
It was found that the only equipment which would not remain in its emergency mode, were, under certain circumstances, some sampling valves. These sampling valves are closed by a containment isolation signal and will return to the open position when the containment isolation signal
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is reset following an actuation.
The following valves are in this category:
i CA-V1 Pzt. Steam Space Sampling CA-V2 R.C. Sampling CA-V3 Pzr. Water Space Sampling CA-V4A Steam Generator A Sampling CA-V4B Steam Generator B Sampling CA-V5A Steam Generator A FW Sampling CA-V5B Steam Generator B FW Sampling CA-V13 R.C. Letdown Sampling Each of these valves has a control switch both in the control room n:d' on a local sampling panel. The sampling panel switches are momentary contact CLOSE-OPEN switches with spring return to a neutral positi :n.
The control room switches are maintained contact, three position, CLOSE, REMOTE, OPEN.
When the control room switch is 6a REMOTE position, the valve may be controlled from the sampling panel.
When the switch is left in either the CLOSE or OPEN position, control from the sampl*ng panel is disabled.
If the control rocm switch is left in the OPEN posit ion after a containment isolation actuation.sigual, the valve will return to the OPEN position when the actuation signal is reset.
Since the control switch is normally returned to the ROiOTE position af ter use, it is unlitely that such a situation would occur.
ITEM 2:
Verify the actual installed instrumentation and controls at the 'acility are consistent with the schematic reviewed in Item I above by conducting a test to demonstrate that all equipment remains in its emergene)_ mode upon removal.of the actuating signal and/or manual resetting of the v4rious isolating or actuation _ signals. Provide a schedule for the performance of the testing in your response to this bulletin.
. RESPONSE:
Following modifications of the ESAS systems for the revised containment isolation, and block 5 load, a test will be conducted to assure that response of components are consistent with the design. The test will be conducted when plant conditions permit and is expected to be complete by February 28, 1981.
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_2-Attachnent i TLL 293 ITEM 3:
If any of the safety related equipment does not remain in its emergency mode upon reset of an ESF signal at year facility, describe proposed system modifications, design changes, or other corrective actions planned to resolve the problem.
RESPONSE
This problem will be corrected by replacing the control room switches with ones that are maintained contact in the CLOSE position and momentary contact in the OPEN position with spring return to REMOTE.
This will prevent the occurrence of the situation described above and will allow the control room operator to override the sampling panel control when the valve needs to be closed. These modifications will be designed and installed by the first refueling outage after restart of TMI-I.
In the interim, the problem will be prevented by adherence to procedures which will specifically prohibit any.of the control switches in question from being left in the OPEN position.
The review of the elementary diagrams showed that the remainder of the ES actuated components at IMI-I remain in their energency position after reset of the actuation signal.
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