ML20127G696
| ML20127G696 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 05/15/1985 |
| From: | Standerfer F GENERAL PUBLIC UTILITIES CORP. |
| To: | Snyder B Office of Nuclear Reactor Regulation |
| References | |
| 0248A, 248A, 4410-85-L-0107, 4410-85-L-107, NUDOCS 8505210118 | |
| Download: ML20127G696 (3) | |
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GPU Nuclear Corporation NUCIMr Post Office Box 480 Route 441 South Middletown, Pennsylvania 17057-0191 717 944 7621 TELEX 84 2386 Writer's Direct Dial Number:
(717) 948-8461 4410-85-L-0107 Document ID 0248A May 15,1985 TMI Program Office Attn: Dr. B. J. Snyder Program Director US Nuclear Regulatory Commission Washington, DC 20555
Dear Dr. Snyder:
Three Mile Island Nuclear Station, Unit 2 (TMI-2)
Operating License No. DPR-73 Docket No. 50-320 Equipment Hatch Removal Safety Evaluation Report Response to NRC Questions The attsched responds to q(uestions concerning the Equipment Hatch Removal Safety Evaluation Report SER) which were forwarded by NRC Letter NRC/TMI 85-025 on April 8, 1985. The subject SER was submitted via GPU Nuclear letter 4410-85-L-0006 dated January 18, 1985.
As noted in NRC/TMI 85-025, GPU Nuclear intended to remove the equipment hatch on a contingency basis, if the need arose. However, planning had been progressing to remove the airlock barrel from the hatch from time-to-time to facilitate the movement of equipment. A more recent evolution of recovery planning now indicates that removal of the airlock barrel may not be necessary. Consequently, GPJ Nuclear requests NRC approval, subject to prior notification, to remove the equipment hatch airlock barrel on a contingency basis.
Since no specific need has been establithed at this time, GPU Nuclear commits to provide written notificat. ion to the NRC as soon as possible after identification of a specific need and, in any case, prior to removal of the airlock.
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GPU Nuclear Corporation is a subsidiary of the General Public Utilities Corporation
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. Dr. B..J.'Snyder May 15,1985 4410-85-L-0107 The need to' remove the entire equipment hatch will continue to be assessed and, if such a need is identified, an appropriate request for PEC approval will be forwarded based on the subject SER.
Sincerely,
/
F. R. Standerfer
' Vice President / Director, THI-2 FRS/RBS/eml
' Attachment cc:
Deputy Program Director - TMI Program Office, Dr. W. D. Travers I
e ATTACHMENT (4410-85-L-0107)
NRC COMENTS AND RESPONSES ON EQUIPENT HATCH REMOVAL QUESTION 1 How long will it tak'e to replace the airlock and how will.it be tested after replacement?
RESPONSE
It is estimated that replacement of the airlock barrel will take one working day. Installation of the airlock will be performed via a Unit Work Instruction. Prior to replacement, the mounting flange 0-Rings will be replaced. After replacement of the airlock, the mounting flanges and 0-Rings will be tested by pressurizing the space between the 0-Rings using an originally installed test fitting. Test criteria will be documented using an approved Startup and Test procedure.
~ QUESTION 2 How will you measure effluents when the airlock is being removed / replaced and the reactor building purge is not operating?
RESPONSE
The air in the vicinity of the equipment hatch will be contained by the Containment Air Control Envelope (CACE) during operations involving removal of the equipment hatch. The CACE is supplied with dual ventilation trains which
-are each monitored by local stationary-filter continuous air monitor (AMS-3).
These monitors will sample the ventilation system downstream of the installed HEPA filters. In addition, continuous air monitoring equipment will be installed to monitor ambient air in the CACE itself.
QUESTION 3 Will the removal and replacement result in any modifications to the penetrations?
RESPONSE
No. Removal of the airlock barrel will require the disconnection of various mechanical and electrical connections. The ability to disconnect and reconnect these connections is included in the design of the airlock; thus this does not constitute a modification to the penetration.
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