ML17256A502
| ML17256A502 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 02/18/1983 |
| From: | Maier J ROCHESTER GAS & ELECTRIC CORP. |
| To: | Crutchfield D Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8302230495 | |
| Download: ML17256A502 (6) | |
Text
REGULATORY FORMATION DISTRIBUTION SY M (RIDS)
ACCESSION NBR:8302230495 DOC ~ DATE: 83/02/18 NOTARIZED ~
NO DOCKET 0
,:FACIL:50"244 Rober(
Emmet Ginna Nuclear Planti Uni;t 1r Rochester G
05000200 AUTH ~ NAME AUTHOR AFFILIATION MAIERgJ ~ ED Rochester'Gas 8 Electric Corp+
iAHCIP, t<AME RECIPIENT AFFILIATION CRUTCHF IELDg D ~
Operating Reactors Branch 5
SUBJECT:
Describes cable.penetration mod:to be performed during spring refueling outage scheduled for late l4ar 1983>No Tech Spec mod nequ'irede DI'STRIBUTION CODE:
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ROCHESTER GAS AND ELECTRIC CORPORATION
~ 89 EAST AVENUE, ROCHESTER, N.Y. 14649 JOHN E. MAIER VRe Pre sfdont TCLCPHOMC ARCA COOC Tld 546-2700 February 18, 1983 Director of Nuclear Reactor Regulation Attention:
Mr. Dennis M. Crutchfield, Chief Operating Reactors Branch No.
5 U.S. Nuclear Regulatory Commission Washington, D.C.
20555
Subject:
Cable Penetration Modification R. E. Ginna Nuclear Power Plant Docket No. 50-244
Dear Mr. Crutchfield:
During the spring refueling outage scheduled to begin in late March 1983, as in past outages, an extensive inspection and main-tenance program will be performed in the steam generators.
These efforts require various power and instrumentation cables to be run through the personnel doors of the equipment hatch allowing the control of some maintenance activities from outside containment thereby reducing occupational exposure.
In past outages, refueling and work requiring these cables could not be performed simultaneously because there was no means to provide during refueling containment integrity without closing personnel
- doors, thereby requiring removal of the cables.
For the spring 1983 refueling outage, a containment closure device will be fabricated to provide a containment isolation barrier during refueling activities.
The closure device will include pipe sleeves capable of housing required cable and hose in an airtight configuration when the containment environment is at atmospheric pressure.
Both doors of the equipment hatch will be opened and the closure device will be mounted to the equipment hatch outside door framing.
The closure device will only be used during refueling conditions.
By using this closure device during refueling outages, we will be able to perform refueling operations simultaneous with steam generator inspection and repair, thus reducing outage critical path time.
We have reviewed the events analyzed in the Ginna Station FSAR and the events requiring analysis by NRC Regulatory Guide
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t ROCHESTER GAS AND ELECTRIC CORP.
DATE February 18, 1983 To
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Mr. Dennis M. Crutchf ield SHEET NO.
2 1.70.
Since the RCS temperature
(<140 F) and core reactivity conditions
(>10%
k/k subcritical) during refueling do not provide the potential energy to pressurize containment, the airtight closure device is sufficient to prevent the spread outside containment of radioactivity released from a fuel assembly damaged during refueling.
Therefore the health and safety of the public would not.be threatened by use of this closure device.
The closure device will satisfy the requirement of Section 3.8.1 of the Ginna Station Technical Specifications that during refueling operations at least one door in each personnel air lock be properly closed.
We do not anticipate making any change to our Technical Specifications due to the use of this device.
This letter is provided for your information.
Very truly yours, J.
. Maier
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