ML17255A549
| ML17255A549 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 11/21/1983 |
| From: | Maier J ROCHESTER GAS & ELECTRIC CORP. |
| To: | Crutchfield D Office of Nuclear Reactor Regulation |
| References | |
| RTR-NUREG-0737, RTR-NUREG-737, TASK-2.B.2, TASK-TM NUDOCS 8311280170 | |
| Download: ML17255A549 (6) | |
Text
REGULATOR NFORMATION DISTRIBUTION TEM (RIDS)
ACCESSION NBRe6311280170 DOC,DATE: 83/11/21 NOTARIZED:
NO DOCKET FACIE:50 244'Robert Emmet Glnna Nuolear Plantr Unl,t Ir Rooneater 0
05000244 Ao'rH,NAME
'UTHOR AFFILIATION MAIERgJ ~ EG Rochester Gas' Electric Corp+
AECiP,NAME RECIPIENT AFFILIATION
Operating Reactors Branch 5
SUBJECT:
Advises that requirements of NUREG 0737~Item II,B;2 re plant shielding design review fulfilled.Const'continuing. on subsequent phases of radwaste control panel mods<
DISTRI8UTION CODE:
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TMI Action Plan Rgmt NURE '737 8
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ROCHESTER GAS AND ELECTRIC CORPORATION
~ 89 EAST AVENUE, ROCHESTER,,N.Y.
14649 JOHN E. MAIER Vice Preskient TELEPNONE AREA coDE 7le 546-2700 November 21, 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:
NUREG 0737, Item II.B.2, Plant Shielding R.
E. Ginna Nuclear Power Plant Docket No.
50-244
Dear Mr. Crutchfield:
TMI Action Plan Requirements specified that a radiation and shielding design review be performed of spaces that may contain highly radioactive material following an accident.
The purpose of the review was to increase the "capability of operators to control and mitigate the consequences of accidents".
The review was to include vital area spaces which were defined as areas "which will or may require occupancy to permit an operator to aid in the mitigation of or recovery from an accident".
Radwaste control stations were suggested as areas to be considered for review.
RG&E performed the required review and in previous letters (see our letters dated December 15,
- 1980, September 4,
- 1981, November 25, 1981 and December',
1982) described the results of the reviews and the resulting plant modifications.
Included among the modifications was a
new radwaste remote control system.
- However, as we stated in previous submittals, it was difficult to
, define under what circumstances the radwaste system might be used following accidents with high source terms.
The post accident objectives identified for 'the shielding review for radwaste systems were to retain the access necessary to terminate releases, to limit the radioactivity that might be transferred to the auxiliary building and to monitor important system parameters.
A detailed review of existing controls showed that no additional control capability was necessary.
Required control capability is available remotely in the control room. It was determined that remote indication of certain parameters would facilitate use of components of the radwaste systems during post accident condi-tions.
Thus, installation of remote indication for the parameters 8311280170 831121 PDR ADOCK 05000204 P
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ROCHESTER GAS AND ELECTRIC CORP.
DATE November 21, 1983 To Mr. Dennis M. Crutchf ield SHEET NO.
listed below constitutes the additional capability necessary to meet the requirements of NUREG-0737.
- 1) LI-1001
- 2) LI-153
- 3) LI-154
- 4) LI-156
- 5) PI-1036
- 6) PI-1037
- 7) PI-1038
- 8) PI-1039
- 9) PI-1025
- 10) PI-155
- 11) PI-1066
- 12) PI-1004
- 13) LI-1003
- 14) TI-1058 Waste Holdup Tank Level 1C CVCS Hold-up Tank Level lB CVCS Hold-up Tank Level 1A CVCS Hold-up Tank Level lA Gas Decay Tank Pressure 1B Gas Decay Tank Pressure 1C Gas Decay Tank Pressure 1D Gas Decay Tank Pressure Vent Header Pressure CVCS Gas Pressure Nitrogen Pressure RCDT Pressure RCDT Level RCDT Temperature These indications are available at two operating terminals remote from the panel as well as at the panel itself.
The terminals are located in the Technical Support Center and at the auxiliary building drumming station.
All modification work for this phase has been completed and the terminals and indications have been tested.
A procedure has been implemented on the use of the equipment, and several operators on each shift have been trained to use the terminals.
- Thus, the TMI requirement to not unduly limit access to areas such that the operators can control and mitigate the consequences of an accident with no undue radiation exposure has been met.
Although the TMI requirements have been met, construction work continues on subsequent phases of the radwaste control panel modifications.
The additional work will provide additional system process indication and remote control capability for most radwaste processing subsystems which will improve operator productivity and reduce normal occupational radiation exposure.
These additional modifications are not necessary to meet TMI requirements.
Very truly yours, J.
E. Maier
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