ML20209B992
| ML20209B992 | |
| Person / Time | |
|---|---|
| Site: | Callaway  |
| Issue date: | 04/22/1987 |
| From: | Blosser J UNION ELECTRIC CO. |
| To: | Davis A NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| References | |
| 87-02, 87-2, ULNRC-1495, NUDOCS 8704280561 | |
| Download: ML20209B992 (5) | |
Text
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.. yg,og Etscraic PE April 22, 1987 CMaway Plant Mr. A. Bert Davis Regional Administrator
'4,
U. S. Nuclear Regulatory Commission Region III 799 Roosevelt Road Glen Ellyn, IL 60137 fl ULNRC-1495
Dear Mr. Davis:
DOCKET NUMBER 50-483 CALLAWAY PLANT UNIT 1 FACILITY OPERATING LICENSE NPF-30 SPECIAL REPORT 87-02 REACTOR COOLANT SPECIFIC ACTIVITY IN EXCESS OF TECHNICAL SPECIFICATION 3.4.8 LIMITATION Theenc'losedSpe.c(alReportissubmittedpursuantto
- Technical Specific $' tion 3.4.8 conc.erning the Reactor Coolant specifid,
~
f activity in excess of Technical Specificetion limitations.
4D BAmJ J. D. Blosser Manager, Callaway Plant MS SM-L JRPe/IPS/JMK/drs Enclosure cc: Distribution attached I
l 8704280561 870422 gDR ADOCK 05000483 PDR 49E g #
Mahng Aatkess PO. Box 62Q Fulton, MO 65251
cc distribution for ULNRC-1495 f
Mr. Thomas W. Alexion (2 copies)
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 Wolf Creek Nuclear Operating Corp.
American Nuclear Insurers P. O. Box 411 c/o Dottie Sherman, Library Burlington, KS 66839 The Exchange Suite 245 270 Farmington Avenue Mr. Merlin Williams Farmington, CT 06032 Supt. of Regulatory Quality &
Administrative Services Records Center Wolf Creek Nuclear Operating Corp.
Institute of Nuclear Power Operations P. O. Box 411 Suite 1500 Burlington, KS 66839 1100 Circle 75 Parkway Atlanta, GA 30339 U. S. Nuclear Regulatory Commission Document Control Desk NRC Resident Inspector Attn Chief, Core Performance Branch and Chief Accident Evaluation Branch D. F. Schnell (400)
Washington, DC 20555 R. J. Schukai (470)
G. L. Randolph J. F. McLaughlin J. E. Davis (Z40SR)
(Z40SR) (w/c)
D. W. Capone /R. P. Wendling (470) e F. D. Field (480)
~
A. P.-Neuha(fen A. C. Passwater/D. E. Shafer/D. J. Walker (470) 4 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 I
JDB Chrono 3456-0021.6 3456-0260 Z40ULNRC G56.37 N. Date (Sandra Auston) (470) l
6 SPECIAL REPORT 87-02 REACTOR. COOLANT SPECIFIC ACTIVITY IN EXCESS OF TECHNICAL SPECIFICATION 3.4.8 LIMITATION This Special Report is submitted in accordance with Technical Specification (T/S) 3.4.8 because the specific activity of the Reactor Coolant System (RCS) exceeded 1.0 microcurie per gram ( C1/gm) Dose Equivalent I-131.
On 4/2/87 at 1202 CST the dose equivalent I-131 of the RCS was sampled and found to be 1.143 pCi/gm. The value during normal operation for the past two months has been approximately.02 pC1/gm. This increase in activity followed a reactor trip (refer to LER 87-002-00).
The cause of the high dose equivalent I-131 is fuel cladding defects.
Licensed operators entered the applicable action statement'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 analysis 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 1552 CST on 4/2/87, at which time the RCS specific activity was restored within limits.
.e The following information is provided per T/S 3.4.8 action statement requirements:
a) Reactor power history is as follows:
From 3/31/87 at 1202 CST to 4/2/87 at 0200 CST, reactor power was at 98%.
From 4/2/87 at 0200 CST to 4/2/87 at 0900 CST, reactor power was decreased from 98%, 0% at a rate of 15% per hour.
From 4/2/87 at 0900 CSI so 4/2/87 at 0907 CST reactor power was 0%.
On 4/2/87 at 0907 CST, a reactor trip occurred.
Power remained at 0% for the duration of the time that the dose equivalent I-131 (DEI-131) limit was exceeded.
b) The results of the isotopic analysis for radiciodine are:
Date Time DEI-131 I-131 I-132 I-133 I-134 I-135 (pci/gm)
(pC1/gm)
(pCf/gm)
(pci/gm)
(pCi/gm)
(pCi/gm) 4/2/87 1035
.562
.414
.227
.448
.022
.226 4/2/87-1202 1.143
.867
.331
.849
.018
.407 4/2/87 1410 1.010
.780
.198
.736
.000
.285 4/2/87 1552
.968
.758
.138
.690
.000
. 227
a SPECIAL REPORT 87-02 Page 2 c) The cleanup flow through the Chemical Volume and Control System mixed bed demineralizer was 120 gallons per minute (gpm) for 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, with the exception of the period from 0919 to 0922 CST on 4/2/87 when letdown was secured. The cleanup flow remained at 120 gpm while the DEI-131 was above 1 pCi/gm.
d) The Volume Control Tank was on a continuous vent of 0.7 cubic feet per minute for 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> prior to the DEI-131 exceeding 1 pCi/gm. This is the only degassing operation that occurred.
e) The DEI-131 exceeded 1 pCi/gm for 3.8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> from 1202 to 1552 CST on 4/2/87.
Also provided for your.information is a time line graph comparing the power level, I-131 specific activity and I-133 specific activity.
Fuel cladding defects have been previously identified on 8/25/86 and 1/30/87 when the DEI-131 exceeded 1 pCi/gm. These events were reported via Special Report 86-07, ULNRC-1374, dated 9/23/86 and Special Report 87-01, ULNRC-1452, dated 2/27/87, respectively.
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