ML20214H622
| ML20214H622 | |
| Person / Time | |
|---|---|
| Site: | Byron  |
| Issue date: | 05/14/1987 |
| From: | Ainger K COMMONWEALTH EDISON CO. |
| To: | Davis A NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| References | |
| NUDOCS 8705270436 | |
| Download: ML20214H622 (3) | |
Text
.-
jm ComHMNNWealth Edloon b
a.
c7 e
p_ Reply 12 Post Omco Box 767
/ Address s Chicago,innois 60800 - 0767 PRIORITY ROUTING May 14, 1987 i riest
- }gAIL Bh _
2 h,0
-1. ]
h+M
~
~
J Mr. A. Bert Davis Ni-
[
~
(It%N Regional Administrator q
t U.S. Nuclear Regulatory Commission guf h.
Region III 799 Roosevelt Road Glen R11yn, IL 60137
Subject:
Byron Station Unit 2 Initial Test Progam NRC Docket No. 50-455
Dear Mr. Davis:
This is to inform you of a change to the Byron Unit 2 Startup Test i
Program made in accordance with 10 CFR 50.59.
This change is being reported I
in accordance with Facility Operating License NPF-66 condition 2.C(3).
FSAR Table 14.2-73 (attached) describes radiation surveys that are performed during power escalation (3-10%, 48-52% and 90-100% power) at pre-selected points throughout the plant.
The change to this test involves radiation surveys being taken at other points in the plant in addition to the originally pre-selected points. The additional measurements are only being made between 90 and 100% power. A safety evaluation of this change is j
attached.
Please direct any questions regarding this matter to this office.
Very truly yours, p.2, =d &
gfv1 K. A. Ainger Nuclear Licensing Administrator Attachments cc:
L.N. Olshan - NRR 1
I 8705270436 870514-DR ADOCK 05000455 PDR
-v\\
3092K i l I
VAY 201983 4
d
+
y--
w
- ,w
,-y-v-1i,w.,-...--,,vy, y,--..--wm--,w-=-==,--,-v
-+-w, r,
v.
ww w -
-5..,w w+-,-e-
--r---t
m,,,w w i, 4,w.
w-grv y.-,r-evtv-,
e
l B/B-FSAR AMEMNGNT 45 j-JUNE 1984 l
i TABLE 14,2-73 RADIATION 50RVEYS (startup Tests)
Plant Condition or Prereuuisite At steady-state conditions during power escalation.
Test Objective
/
To determine dose-levels at preselected points throughout the plant and to verify the effectiveness of radiation shielding.
Teat summary Radiation surveys will be made during power escalation to determine dose-levels at preselected points'throughout the plant due to neutron and gamma radiation.
Instruments used will be calibrated to known sources and the calibration re-checked following the survey.
Surveys will be conducted at steady-state conditions at approximately 3-104,48-524, and 90-1004 power.
Acceptance Criteria Neutron and gamma radiation dose levels are in accordance with Table 12.3-2.
I
_1
ATTACEMENT Startup Test Procedure Radiation Surveys During Power Ascension (2 61.83)
Date of change 4/14/87 Descript!on She changes made, that pertain to ifcense condition 2.C.4, deletes the requirement to take radiation survey data at newly designated Radiation Base Points (RBP) at power levels less than 90-100% power.
Safety Evaluation:
1.
The probability of an occurrence or the consequence of an accident, or malfunction of equlpment important To safety u previously evaluated in the F8AR is not increased. 'Ihis is because survey data will be taken at the 90% to 100% power level which should provide the highest dose rates for the RSP's. Anticipated does rates at the new RBPis should not affect the qualification of safety related equipment.
2.
The possibility for an accident or malfunction of a different type than previously evaluated in the PSAR la not created. This la because survey data will determine the effectivenean of radiation shleIding design as referenced in PSAR 8ection 12.3. New RBP's are generally in the ytcinity of other RBP's and therefore it is not expected for the does rates at the new RBP's to have any effect on the qualification of safety related equipment.
3.
The margin of safety, as defined in the basis for any Technical 5peelftcation, is not reduced. This is because the lack of survey data at lower power levels wlIl not prevent station personnel entry into these areas for the performance of essential tasks. Likewise, the lack of survey data will not affect the qualification of safety related equipment.
- 50/041
....