ML20070S488
| ML20070S488 | |
| Person / Time | |
|---|---|
| Site: | Grand Gulf  |
| Issue date: | 02/02/1983 |
| From: | Dale L MISSISSIPPI POWER & LIGHT CO. |
| To: | Harold Denton Office of Nuclear Reactor Regulation |
| References | |
| AECM-83173, NUDOCS 8302040426 | |
| Download: ML20070S488 (3) | |
Text
o P MISSISSIPPI POWER & LIGHT COMPANY Helping Build Mississippi P. O. B O X 164 0, J A C K S O N, MISSISSIPPI 39205 February 2, 1983 NUCLEAR PRooUCTioN DEPARTMENT U. S. Nuclear Regulatory Commission Office of Nuclear Reactor Regulation Washington, D. C. 20555 Attention: Mr. Harold R. Denton, Director
Dear Mr. Denton:
SUBJECT:
Grand Gulf Nuclear Station Units 1 and 2 Docket Nos. 50-416 and 50-417 License No. NPF-13 File 0260/15180
Reference:
AECM-82/626 AECM-83/012 AECM-83/32 Request for Additional Information - Protective Sleeves for LPRMs AECM-83/73 Attached are the Mississippi Power & Light's (MP&L) responses to the Nuclear Regulatory Commission (NRC) review questions as discussed by telephone on February 2, 1983 with Mr. Dean Houston and Frank Skopec of your staff.
As discussed in the above mentioned telephone conference, MP&L is also requesting that the provisions of proposed Operating License Condition Item 2.C(42)i be extended to include reinstallation of vibration monitoring equipment so that this item would read as follows:
1.
the provisions of Specification 3.9.11 may be suspended for the purpose of replacing startup sources and reinstalling vibration monitoring equipment.
Specification 3.9.11 requires at least one shutdown cooling loop in operation. Some of the vibration monitoring instrumentation equipment must be reinstalled near the feedwater spargers.
MP&L feels that operation of shutdown cooling during this operation would be an unnecessary risk to personnel working in this area.
3 Col 8302040426 B30202 PDR ADOCK 05000416 P
PDR Member Middle South Utilities System
- E*
MICOl2'2tPPI POWER O LI2HT COMPANY If additional information is required, please advise.
Yours truly,
/ U L. F. Dale Manager of Nuclear Services J0F/SHH/JDR: sap Attachment cc: Mr. N. L. Stampley (w/o)
Mr. R. B. McGehee (w/o)
Mr. T. B. Conner (w/o)
Mr. G. B. Taylor (w/o) 4 Mr. Richard C. DeYoung, Director (w/a)
Office of Inspection & Enforcement U. S. Nuclear Regulatory Commission Washington, D. C.
20555 Mr. J. P. O'Reilly, Regional Administrator (w/a)
Office of Inspection and Enforcement U.S. Nuclear Regulatory Commission Region II 101 Marietta St., N.W., Suite 3100 Atlanta, Georgia 30303
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Attschment AECM-83/73 Response to Nuclear Regulatory Commission concerns regarding radiological assessment of radiation levels in the work crea.
9.1 Concern What radiation levels are expected in the work area?
Response
During August of 1982, af ter initial fuel. load, a radiation survey was made which measured radiation levels at the top of the core with water level lowered to just bclow the top guide. The survey was made for the installation the vibration monitoring equipment on the fuel bundles. The dose rate at this time was 2.5 mr/hr; 1.5 from neutrons and 1.0 from gamma.
The work procedure in question will require water level to be approximately eighteen (18) inches lower than during the above survey but the sources will have decayed for about six months [ weaker by a factor of eight (8)].
Considering the fact that most of the shielding of radiation is from the fuel, the lower water level will have a negligible effect. The net result is that radiation icvels will be no higher than the above survey.
9.2 Cnneern What is the maximum expected dose rate of one fuel assembly in air?
Response
Our calculations show that the maxim'im possible dose would be ten (10) mr at a distance of one (1) foot or two (2) mr at a distance of one (1) meter.
9.3 Concern What is the total estimated personnel exposure?
Response
i Using the 2.5 mr/hr figure (which would be very conservative), a maximum of five people in the work area at one time, five working days (three shifts per day), the total estimated personnel expo; ore would be no greater than 1.5 man-rem, f
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