ML20214X405
| ML20214X405 | |
| Person / Time | |
|---|---|
| Site: | Callaway  |
| Issue date: | 09/23/1986 |
| From: | Randolph G UNION ELECTRIC CO. |
| To: | Berlinger C, Milhoan J Office of Nuclear Reactor Regulation |
| References | |
| 86-07, 86-7, ULNRC-1374, NUDOCS 8610030445 | |
| Download: ML20214X405 (5) | |
Text
r Union Etscraic 85 Callaway Plant September 23, 1986 Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission 7920 Norfolk Avenue Bethesda, MD 20014 Attention Plant System Branch Chief James L. Milhoan Mail Stop 416 Reactor System Branch Chief Carl H. Berlinger Mail stop 544 ULNRC-1374 Gentlemen:
DOCKET NUMBER 50-483 CALLAWAY PLANT UNIT 1 FACILITY OPERATING LICENSE NPF-30 SPECIAL REPORT 86-07 SPECIFIC ACTIVITY OF REACTOR COOLANT EXCEEDS TECHNICAL SPECIFICATION 3.4.8 LIMITATION The enclosed Special Report is submitted pursuant to Technical Specification 3.4.8 concerning specific activity of the Reactor Coolant exceeding the required limit.
G. L. Randol h Manager, Callaway Plant WRB JR e/TP /WRB/drs Enclosure cc: Distribution attached 8610030445 860923 o
PDR ADOCK 05000483 n,0 S
pop.
g
\\
l Madrx] Address P.O. Box 620, Futton, MO 65251
f cc distribution for ULNRC-1374 Mr. Paul O'Connor Manager, Electric Department Office of Nuclear Reactor Regulation Missouri Public Service Commission U.S. Nuclear Regulatory Commission P. O. Box 360 Mail Stop P-316 Jefferson City, MO 65102 7920 Norfolk Avenue Bethesda, MD 20014 Mr. O. Maynard Kansas Gas and Electric Company P. O. Box 208 American Nuclear Insurers Wichita, KS 62701 c/o Dottie Sherman, Library The Exchange Suite 245 Mr. Nicholas A. Petrick 270 Farmington Avenue Executive Director, SNUPPS Farmington, CT 06032 5 Choke Cherry Road Rockville, MD 20850 Mr. J. H. Smith Bechtel Power Corporation Records Center SNUPPS Project Institute of Nuclear Power Operations 15740 Shady Grove Road Suite 1500 Gaithersburg, MD 20877-1454 1100 Circle 75 Parkway Atlanta, CA 30339 Mr. James G. Keppler Regional Administrator Mr. Merlin Williams Office of Inspection & Enforcement Supt. of Regulatory Quality &
U.S. Nuclear Regulatory Commission Administrative Services Region III Kansas Gas and Electric Company 799 Roosevelt Road P. O. Box 309 Glen Ellyn, IL 60137 Burlington, KS 66839 NRC Resident Inspector Mr. Harold R. Denton D. F. Schnell (400)
Director R. J. Schukai (470)
Office of Nuclear Reactor Regulation S. E. Miltenberger U.S. Nuclear Regulatory Commission J. F. McLaughlin Mail Stop P-428 J. E. Davis (Z40LER) 7920 Norfolk Avenue (240LER) (w/c)
Bethesda, MD 20014 D. W. Capone /R. P. Wendling (470)
F. D. Field (480)
A. P. Neuhalfen A. C. Passwater/D. E. Shafer/D. J. Walker (470)
G. A. Hughes Z40.03 (QA Record)
J. M. Price J. R. Peevy M. E. Taylor H. Wuertenbaecher, Jr. (100)
S. L. Auston (470)(NSRB)
S. J. Bellers/J. D. Schnack GLR Chrono 3456-0021.6 3456-0260 Z40ULNRC G56.37 N. Date (Sandra Auston) (470)
I
(
SPECIAL REPORT 86-07 SPECIFIC ACTIVITY OF REACTOR COOLANT EXCEEDS TECHNICAL SPECIFICATION 3.4.8 LIMITATION This report is being submitted in accordance with the Technical Specification 3.4.8.
It requires that a Special Report be submitted to the Commission pursuant to Specification 6.9.2 when the specific activity of the Reactor Coolant System (RCS) is greater than 1.0 microcurie per gram (pci/gm) DOSE EQUIVALENT I-131.
On 8/25/86 at approximately 1000 CDT the dose equivalent I-131 of the RCS was sampled and found to exceed Technical Specification (T/S) 3.4.8 with a value of 1.14 pci/gm. The value during normal operation has been approximately.04 pei/gm. This increase of dose equivalent I-131 followed a manual reactor trip at 0706 CDT on 8/25/86 which is being reported as Licensee Event Report 86-029-00.
The root cause of this higher than normal dose equivalent I-131 is due to defects in cladding of the fuel. The utility licensed operators entered the applicable action statement. That action statement is as follows:
"With the specific activity of the reactor coolant greater than 1.0 microcurie per gram DOSE EQUIVALENT I-131 or greater than 100/E microCuries per gram of gross radioactivity, perform the sampling and analyses requirements of Item 4.a) of table 4.4-4 until the specific activity of the reactor coolant is restored to within its limits... "
Appropriate sampling and analysis requirements were performed until the RCS specific activity was restored to within limits. This occurred at approximately 1400 on 8/25/86.
The T/S action item requires this Special Report to contain the following information:
a) Reactor power history is as follows:
8/23/86, 1000 to 8/25/86, 0633 Reactor power was 100%
8/25/86, 0633 to 0706 Reactor power was reduced from 100% to 70%
8/25/86 0706 Reactor was manually tripped and power remained at 0% for the duration of the time the Dose Equivalent I-131 (DEI-131) limit was exceeded, b) Results of the isotopic analysis for radioiodine were:
DEI-131 I-131 I-132 I-133 I-134 I-135 Date/ Time (uci/gm)
(uci/gm)
(uci/gm)
(uci/gm)
(uci/gm)
(pci/gm) 8-25-86/0756
.732
.486
.461
.707
.142
.431 8-25-86/1000 1.14
.823
.457
.955
.047
.501 8-25-86/1200 1.04
.779
.299
.815
.013
.381 8-25-86/1400
.872
.666
.213
.651
.00
.263
SPECIAL REPORT 86-07 Page 2 c) Clean-up flow through the Chemical and Volume Control System mixed bed demineralizer was at maximum flow, 120 gallons per minute, 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> prior to exceeding 1 pci/gm DEI-131 and the clean-up flow remained at 120 g.p.m while DEI-131 was above 1 pei/gm.
d) The Volume Control Tank was on a continuous vent of 0.7 cubic feet per minute 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> prior to DEI-131 exceeding 1 pei/gm. This is the only degassing operation that occurred.
e) The DEI-131 exceeded 1 pci/gm for 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, from 1000 to 1400 on August 25, 1986.
Also provided for your'information is a time line graph of the Power Level, I-131 pei/gm, and I-133 pei/gm.
..__.__.__.________..__________________J
..a.,
-...~~.---wo--
-. - - -.. ~
~ ~ * ' - ' = = ~ '
w$
%o:o H
\\
\\
\\
4 y
\\
r D'
\\__
Blu
\\
gg g
~~"
O"
\\
-[s d
i
, I
_1 Samplo ID : RC-02 System : BB Limit Type: M1 1.OE+ 00
/ \\
\\
,/
\\
to
/
\\
rq s
/
N r-G 7
N
/
\\
lh
\\
0.CE*00
/
Samplo ID : RC-02 Syctem : BB 1.CE+ CO
,N
/ _.
A J
N_
tq y
_/;
N "R
N
=
C i g,,,
__7 C:V24N,6 Ov25cs Cv2&to 06/27/55 Ctv2 MSS
- - - - - - ~ ~ - ~ ~ ~ - - -
~ ~ -
S
.