ML13331B012
| ML13331B012 | |
| Person / Time | |
|---|---|
| Site: | San Onofre  |
| Issue date: | 02/29/1988 |
| From: | Morgan H SOUTHERN CALIFORNIA EDISON CO. |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| References | |
| NUDOCS 8803030211 | |
| Download: ML13331B012 (10) | |
Text
REGULATOW INFORMATION DISTRIBUTIOr*YSTEM (RIDS)
ACCESSION NBR:8803030211 DOC.DATE: 88/02/29 NOTARIZED: NO DOCKET #
FACIL:50-206 San Onofre Nuclear Station, Unit 1, Southern Californ 05000206 50-361 San Onofre Nuclear Station, Unit 2) Southern Californ 05000361
,50-362 San Onofre Nuclear Station, Unit 3, Southern Californ 05000362 AUTH.NAME AUTHOR AFFILIATION MORGANH.E.
Southern California Edison Co.
RECIP.NAME RECIPIENT AFFILIATION Document Control Branch (Document Control Desk)
SUBJECT:
Forwards annual RCS specific activity rept for 1987.Unit 2 activity exceeded limits of Tech Spec 3.4.7 on four separate occasions during 1987 but Units 1 & 3 did not exceed Tech Spec limit.
DISTRIBUTION CODE: AO1D COPIES RECEIVED:LTR JL ENCL _
SIZE:
TITLE: OR Submittal: General Distribution NOTES:License Exp date in accordance with 10CFR2,2.109.
05000206 RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD5 LA 1
0 PD5 PD 5
5 TRAMMELLC 1
1 HICKMAND 1
1 INTERNAL: ACRS 6
6 ARM/DAF/LFMB 1
0 NRR/DEST/ADS7E4 1
1 NRR/DEST/CEB8H7 1
1 NRR/DEST/MTB 9H 1
1 NRR/DEST/RSB BE 1
1 NRR/DOEA/TSB11F 1
1 NR
_ AS/ILRB12 1
1 OGC 15-B-18 1
0 EG FILE 01 1
1 RES/DE/EIB 1
1 EXTERNAL: LPDR 2
2 NRC PDR 1
1 NSIC 1
1 TOTAL NUMBER OF COPIES REQUIRED: LTTR 28 ENCL 25
0 Southem California Edison Company SAN ONOFRE NUCLEAR GENERATING STATION P. 0. BOX 128 SAN CLEMENTE, CALIFORNIA 92672 H.E.MORGAN TELEPHONE STATION MANAGER (714) 368-6241 February 29, 1988 U. S. Nuclear Regulatory Commission Attention:
Document Control Desk Washington, D. C.
20555
SUBJECT:
Docket Nos. 50-206, 50-361 and 50-362 Annual RCS Specific Activity Report San Onofre Nuclear Generating Station, Units 1, 2 and 3 Pursuant to Section 6.9.1.5 of Appendix A, Technical Specifications for Provisional Operating License No. DPR-13 for Unit 1 and Facility Operating Licenses NPF-10 and NPF-15 for Units 2 and 3, respectively, this submittal provides the required Annual Reactor Coolant System (RCS) Specific Activity Report for 1987. Unit 2 RCS specific activity exceeded the limits of Technical Specification 3.4.7 on four separate occasions during 1987.
There were no occasions in 1987 in which Unit 1 or 3 RCS specific activity exceeded Technical Specification limits.
If you require any additional information, please so advise.
Sincerely, Enclosures cc: J. B. Martin, Regional Administrator, USNRC Region V F. R. Huey, USNRC Senior Resident Inspector, Units 1, 2 and 3 Institute of Nuclear Power Operations (INPO)
AOO 8803030211 880229 PDR ADOCK 05000206 R
PAGE 1 OF 4 RCS SPECIFIC ACTIVITY REPORT SOUTHERN CALIFORNIA EDISON COMPANY SAN ONOFRE NUCLEAR GENERATING STATION UNIT NOS. 1, 2 AND 3, DOCKET NOS. 50-206, 50-361 AND 50-362 On February 5, 1987 at 1300, with Unit 2 in Mode 3, following a manual reactor trip, analysis of a RCS sample indicated RCS specific activity exceeded 1.0 microcurie/gram Dose Equivalent (DE) 1-131 due to iodine spiking. RCS specific activity was reduced to less than 1.0 microcurie/gram DE 1-131 by purification flow by 0750 on February 6, 1987. Therefore, the time duration when the specific activity of the primary coolant exceeded the radioiodine limit was approximately 19 hours2.199074e-4 days <br />0.00528 hours <br />3.141534e-5 weeks <br />7.2295e-6 months <br />.
The additional information required by Technical Specification 6.9.1.5 is presented below and in Figure 1.
REACTOR POWER HISTORY Period Reactor Power 2/3/87, 1300 to 2/5/87, 0800 100%
2/5/87, 0800 Reactor Trip 0%
2/5/87, 0800 to 2/5/87, 1300 0%
REACTOR COOLANT SYSTEM SPECIFIC ACTIVITY Date/Time of Sample DE 1-131 (uCi/gram) 2/4/87, 0825 0.756 2/5/87, 1300 2.045 2/5/87, 1700 2.068 2/5/87, 2100 1.782 2/6/87, 0100 1.403 2/6/87, 0456 1.034 2/6/87, 0750 0.714 CLEANUP FLOW HISTORY Period Average Cleanup Flow (gpm) 2/3/87, 1300 to 2/4/87, 0800 77 2/4/87, 0800 to 2/5/87, 0800 82 2/5/87, 0800 to 2/6/87, 0000 72 2/6/87, 0000 to 2/6/87, 0800 85*
- Hourly cleanup flow rate not available. Figure used is taken from average flow with two charging pumps in operation.
PAGE 2 OF 4 RCS SPECIFIC ACTIVITY REPORT SOUTHERN CALIFORNIA EDISON COMPANY SAN ONOFRE NUCLEAR GENERATING STATION UNIT NOS. 1, 2 AND 3, DOCKET NOS. 50-206, 50-361 AND 50-362 On March 17, 1987 at 0953, with Unit 2 in Mode 3, following a reactor shutdown for an outage, analysis of a RCS sample indicated RCS specific activity exceeded 1.0 microcurie/gram Dose Equivalent (DE) 1-131 due to iodine spiking.
RCS specific activity was reduced to less than 1.0 microcurie/gram DE 1-131 by purification flow by 0830 on March 18, 1987. Therefore, the time duration when the specific activity of the primary coolant exceeded the radioiodine limit was approximately 23 hours2.662037e-4 days <br />0.00639 hours <br />3.80291e-5 weeks <br />8.7515e-6 months <br />.
The additional information required by Technical Specification 6.9.1.5 is presented below and in Figure 2.
REACTOR POWER HISTORY Period Reactor Power 3/15/87, 0953 to 3/16/87, 2000 100%
3/16/87, 2000 to 3/17/87, 0001 100% Decreasing to 65%
3/17/87, 0001 to 3/17/87, 0103 65% Decreasing to 48%
3/17/87, 0103 to 3/17/87, 0440 48% Decreasing to 0%
3/17/87, 0440 Reactor Shutdown 0%
3/17/87, 0440 to 3/17/87, 0953 0%
REACTOR COOLANT SYSTEM SPECIFIC ACTIVITY Date/Time of Sample DE 1-131 (uCi/gram) 3/17/87, 0426 0.396 3/17/87, 0953 2.999 3/17/87, 1355 3.219 3/17/87, 1755 2.511 3/17/87, 2155 2.038 3/18/87, 0155 1.437 3/18/87, 0530 1.189 3/18/87, 0830 0.972 CLEANUP FLOW HISTORY Period Average Cleanup Flow (gpm) 3/15/87, 0900 to 3/16/87, 0900 80 3/16/87, 0900 to 3/17/87, 0900 78 3/17/87, 0900 to 3/18/87, 0900 118
PAGE 3 OF 4 RCS SPECIFIC ACTIVITY REPORT SOUTHERN CALIFORNIA EDISON COMPANY SAN ONOFRE NUCLEAR GENERATING STATION UNIT NOS. 1, 2 AND 3, DOCKET NOS. 50-206, 50-361 AND 50-362 On March 28, 1987 at 0402, with Unit 2 in Mode 3, following a reactor trip, analysis of a RCS sample indicated RCS specific activity exceeded 1.0 microcurie/gram Dose Equivalent (DE) 1-131 due to iodine spiking. RCS specific activity was reduced to less than 1.0 microcurie/gram DE 1-131 by purification flow by 1915 the same day. Therefore, the time duration when the specific activity of the primary coolant exceeded the radioiodine limit was approximately 15 hours1.736111e-4 days <br />0.00417 hours <br />2.480159e-5 weeks <br />5.7075e-6 months <br />.
The additional information required by Technical Specification 6.9.1.5 is presented below and in Figure 3.
REACTOR POWER HISTORY Period Reactor Power 3/26/87, 0402 to 3/27/87, 2135 100%
3/27/87, 2135 to 3/28/87, 0100 100% Decreasing to 85%
3/28/87, 0100 Reactor Trip 0%
3/28/87, 0100 to 3/28/87, 0402 0%
REACTOR COOLANT SYSTEM SPECIFIC ACTIVITY Date/Time of Sample DE 1-131 (uCi/gram) 3/27/87, 0745 0.0977 3/28/87, 0402 1.586 3/28/87, 0800 1.822 3/28/87, 1200 1.414 3/28/87, 1600 1.049 3/28/87, 1915 0.869 CLEANUP FLOW HISTORY Period Average Cleanup Flow (gpm) 3/26/87, 0400 to 3/27/87, 0400 80 3/27/87, 0400 to 3/28/87, 0400 77 3/28/87, 0400 to 3/28/87, 2000 103
PAGE 4 OF 4 RCS SPECIFIC ACTIVITY REPORT SOUTHERN CALIFORNIA EDISON COMPANY SAN ONOFRE NUCLEAR GENERATING STATION UNIT NOS. 1, 2 AND 3, DOCKET NOS. 50-206, 50-361 AND 50-362 On August 29, 1987 at 0600, with Unit 2 in Mode 3, following a reactor shutdown for a refueling outage, analysis of a RCS sample indicated RCS specific activity exceeded 1.0 microcurie/gram Dose Equivalent (DE) 1-131 due to iodine spiking.
RCS specific activity was reduced to less than 1.0 microcurie/gram DE 1-131 by purification flow by 0956 on August 30, 1987.
Therefore, the time duration when the specific activity of the primary coolant exceeded the radioiodine limit was approximately 28 hours3.240741e-4 days <br />0.00778 hours <br />4.62963e-5 weeks <br />1.0654e-5 months <br />.
The additional information required by Technical Specification 6.9.1.5 is presented below and in Figure 4.
REACTOR POWER HISTORY Period Reactor Power 8/27/87, 0600 to 8/28/87, 0930 80%
8/28/87, 0930 to 8/29/87, 0001 80% Decreasing to 23%
8/29/87, 0001 to 8/29/87, 0240 23% Decreasing to 0%
8/29/87, 0240 Reactor Shutdown 0%
8/29/87, 0240 to 8/29/87, 0600 0%
REACTOR COOLANT SYSTEM SPECIFIC ACTIVITY Date/Time of Sample DE 1-131 (uCi/gram) 8/28/87, 0821 0.141 8/29/87, 0600 2.124 8/29/87, 0957 2.550 8/29/87, 1400 2.680 8/29/87, 1800 1.860 8/29/87, 2200 1.470 8/30/87, 0155 1.450 8/30/87, 0555 1.170 8/30/87, 0956 0.856 CLEANUP FLOW HISTORY Period Average Cleanup Flow (gpm) 8/27/87, 0600 to 8/28/87, 1200 80 8/28/87, 1200 to 8/29/87, 0000 85*
8/29/87, 0000 to 8/29/87, 0900 94 8/29/87, 0900 to 8/30/87, 1000 78
- Hourly cleanup flow data not available. Figure used is taken from average flow with two charging pumps in operation.
FIGURE 1 2/5/87 TO 2/6/87 2.2 2.0452.068 2
- p9 u
i.6 0
1.371 1.403 z
c 1.4 c:
1.100 1.2 z
us 1.034 1-133 0.795 Ct 0.71A ca 0.8 1-(n
$2 0.540 0.6 0.346 0.4 0.2 III I
I I
1300 1500 1700 1900 2100 2300 0100 0300 0500 0700 TIME (Hrs)
FIGURE 2 3/17/87 TO 3/18/87 4
3.5 3.219 c
3 2.5
-DE I-131 I-4 2.146 2.1022.3 z w 2
z C
C.3 1.476 1.437 w
- a.
1.5 c
1.189 0
1.073 10.972 I--3 0.693 0.516 0.5 0.385 0955 1155 1355 1555 1755 1955 2155 2355 0155 0355 0555 0755 TIME (Hrs)
FIGURE 3 3/28/87 2
1.822 1.8 1.586 1.605 1.6 1.6
-1.52 55 DE I-131 9-1.4 z--133 1.049 w
as 0.889 0.780 0.8 0.0 0.6 0400 0800 1200 1600 2000 TIME (Hrs)
FIGURE 4 8/29/87 TO 8/30/87 3
2.8 2.680 2.550 2.6 a2.4 2.2 1.660 DE I-131 1.8 1.6 0
1.450 0..35 z
1.4 7
a 2
.44 Lf w
1.2 9L a 1-0.872 0.856 II-13 0.8 0.817 0.545 0.6 397 0.4 0.25 0.2 0600 1000 1400 1800 2200 0200 0600 1000 TIME (Hrs)