ML20213D684
| ML20213D684 | |
| Person / Time | |
|---|---|
| Site: | Byron  |
| Issue date: | 10/30/1986 |
| From: | Hunsader S COMMONWEALTH EDISON CO. |
| To: | Harold Denton Office of Nuclear Reactor Regulation |
| References | |
| 2349K, NUDOCS 8611120191 | |
| Download: ML20213D684 (5) | |
Text
-.
A e} CORNRenWealth Eclison
. ?
One First Nabonal Plaza Chca0o, Illinois WJu Reply to: Post Omco Box 767 Chcago, Illinois 60600 - 0767 October 30, 1986 Mr. Harold R. Denton U.S. Nuclear Regulatory Commission Office of Nuclear Reactor Regulation Washington, DC. 20555
Subject:
Byron Station Unit 2 Interim Operation of HVAC System NRC Docket No. 50-455
Reference:
(a)
October 24, 1986 letter from S.C.
Hunsader to H.R. Denton
Dear Mr. Denton:
This letter provides supplementary information to give further detail concerning the leak detection program committed to in reference (a).
The attached procedure SPP-86-160, Revision 0 provides the method of leak testing potentially radioactive systems outside of containment and obtaining an accumulated total leakage.
Leak testing is to be performed prior to 30% power and during the ASME quarterly pump surveillances.
As noted in the procedure, the total ECCS leakage shall be compared to Figure 1 included in reference (a).
In the event the 4
total leakage is greater than the leakage value for a power level, the Shift Engineer shall be notified immediately.
The Shift Engineer shall reduce the leakage to an acceptable value or reduce power in accordance with Figure 1, within six (6) hours.
Should you have any questions, please contact his office.
One signed original and fifteen copies of this letter and the attachment are provided for your review.
i Very truly yours,
/Jcrp S.
C. Hunsader Nuclear Licensing Administrator l
/klj l
cc:
L. Olshan 2349K 1120191 861030 A
DOCK 05000455 PDR Qgc\\
IlI
^
SPP 86-160 Rev. O LEAK TESTING OF POTENTIALLY RADIOACTIVE COMPONENTS OUTSIDE OF CONTAINMENT A.
STATEMENT OF APPLICABILITY:
The purpose of this procedure is to provide a method of leak testing potentially radioactive systems outside of containment, and trending this leakage on a periodic basis. Testing will be performed prior to 30%
reactor power and during the ASME quarterly pump surveillances.
B.
REFERENCES:
1.
III D.l.1, NURBG 0737 2.
LTR 86-1314 From R.E. Querio to K.A. Ainger, dated 10/20/86.
3.
2BVS XII-1, Primary Coolant Sources Outside containment, Visual Examination (Leakage Test)
C.
PRERBOUISITES:
1.
Verify the status of the system being tested is such that this procedure may be performed by obtaining permission from the shift engineer, or his designated SRO licensed assistant.
/
2.
The system being tested must be at its nominal operating pressure (Listed in Attachment A).
/
3.
Notify the Rad / Chem Department prior to initiation of the test to determine RWP requirements.
/
D.
PRECAUTIONS:
1.
Equipment being tested is under pressure, exercise caution while performing exams.
E.
LIMITATIONS AND ACTIONS:
1.
The total ECCS leakage shall be compared to Figure 1 of Section G.
In the event the total leakage is GREATER than the value for that power level, the Shift Engineer shall be notified immediately. The Shift Engineer shall reduce the leakage to an acceptable value or reduce power in accordance with Figure 1 of Section G within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
F.
MAIN BODY:
1.
Perform leak testing of the following.
If only a portion of the list is completed, initial only those portions completed.
Containment Spray A Train
/
B Train
/
Chem /Vol Control A Train
/
B Train
/ -(1109M)
e
~
SPP 86-160 Rev. O Residual Heat Removal A Train
/
B Train
/
Safety Injection A Train
/
B Train
/
2.
RECORD leakage observed (Quantity, GPH) in Table 1 on Data Sheet D-1.
/
- 3.
RECORD the Total Leakage from, BVP 200-T10 and compare this value to Figure 1 of Section G.
/
4.
For subsequent tests, the leakage shall be compared to the previous leakage. The difference shall be noted and added/ subtracted from the Total Leakage
/
G.
ACCEPTANCE CRITERIA:
The Total ECCS Leakage Rate, obtained from Table 1 of Data Sheet 1, will be compared to Figure 1.
This Leakage Rate must be within the limits specified for the applicable reactor power level.
H.
EVALUATION:
Prepared by (1109M)
SPP 86-160 Rev. 0
/ /
TABLE 1 SYSTEM /
LEAKAGE MEASUREMENTS (GALLONS / HOUR)
TRAIN 1
2 3
4 5
6 Baseline Data Containment Spray (CS)/A
/
/
/
/
/
Containment Spray (CS)/B
/
/
/
/
/
Chemical and volume control
/
/
/
/
/
(cv)/A chemical and Volume Control
/
/
/
/
_ _/
(CV)/B Safety Injection (SI) /A
/
/
/
/
/
Safety Injection (SI)/B
/
/
/
/
/
Residual Heat Removal (RH)/A
/
/
/
/
/
Residual Heat Removal (RH)/B
/
/
/
/
/
Total ECCS Leakage t
/
t
/
t
/
t
/
t
/
-DI-Il09M (1109M)
SPP 86-160 Rev. O ATTACHMENT A: SYSTEM NOMINAL OPERATING PRESSURES SYSTEM NOMINAL OPERATING PRESSURE (PSIG) 1.
Containment 1 250 psig Spray (CS) 2.
Chemical and
> 2485 psig Volume Control (CV) 3.
Safety
> 1500 psig Injection (SI) 4.
Residual Heat 2 220 psig Removal (RH) 1411W (1109M)
..