View source for 3F0887-01, Special Rept 87-02:on 870702,reactor Trip Occurred from 88% Rated Thermal Power.Primary Coolant Sample Obtained & Analyzed for Iodine Activity,Per Tech Spec 4.4.8.Reactor Power History,Fuel Burnup & Time Duration Provided

{{Adams
| number = ML20236L003
| issue date = 08/03/1987
| title = Special Rept 87-02:on 870702,reactor Trip Occurred from 88% Rated Thermal Power.Primary Coolant Sample Obtained & Analyzed for Iodine Activity,Per Tech Spec 4.4.8.Reactor Power History,Fuel Burnup & Time Duration Provided
| author name = Simpson E
| author affiliation = FLORIDA POWER &amp; LIGHT CO., FLORIDA POWER CORP.
| addressee name = 
| addressee affiliation = NRC OFFICE OF ADMINISTRATION &amp; RESOURCES MANAGEMENT (ARM)
| docket = 05000302
| license number = 
| contact person = 
| document report number = 3F0887-01, 3F887-1, 87-02, 87-2, NUDOCS 8708100090
| document type = REPORTABLE OCCURRENCE REPORT (SEE ALSO AO LER), TEXT-SAFETY REPORT
| page count = 8
}}

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:                          x. y Florida Power COHPOPATION August 3, 1987 3F0887-01 U. S. Nuclear Regulatory Commission Attn:    Document Control Desk Washington, D.C. 20555                                        ..
1 3ubjet t:  Crystal River Unit 3                                   j Docket No. 50-302                                      l Operating License No. DPR-72 Special Report 87-02

==Dear Sir:==
Enclosed is Special       Report 87-02 which is submitted in accordance with Technical Specification 6.9.2.p.
Should tnere be any questions, please contact this office.
Sincerely, dbck Fur E. C. Simpson Acting Director Nuclear Site Support WLR/sjm Enclosure cc: Dr. J. Nelson Grace                                             l Regional Administrator, Region 2 Mr. T. F. Stetka                                              l Senior Resident inspector 8708.100090 g7ogo3 DR                                      ADOCK 0500030g PDR A Florida Progress Company
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l SUf17ECT: Special Reoort 87-02                                                     i Crystal River Unit 3 experienced a reactor trip from 88% Rated Thermal Pwer at 1043 on July 2, 1987. At 1542, a primary coolant sample was obtained and     j analyzed for iodine activity in accordance with 7bchnical Specification 4.4.8. l The result was 1.275 pCi/gm dose equivalent I-131.        Samples continued to be obtained and analyzed at intervals not exceeding four (4) hours until the dose equivalent iodine coiaud. ration decreased belm 1.0 4Ci/gm.         This report is submitted in accordarvae with Technical Specification 6.9.2.
This report contains the results of the specific activity analysis together with the reactor power history, fuel burnup, and the time duration that the dose equivalent I-131 exceeded 1.0 4C1/gm.
: 1. Reactor Ibwer History:   Forty-eight (48) hours before the dose equivalent I-131 concentration exceeded 1.0 #Ci/gm, the reactor pwer was being maintained at approximately 88% Rated Thermal Pwer. The reactor pwer history is presented in Table I and Figure 1.
: 2. Fuel burnup by core region:   This information is presented in Table 2 and Figure 2.
: 3. Clean-up flow (letdwn flw) history: Reactor coolant letdwn flw forty-eight (48) hours before the dose equivalent I-131 concentration exceeded 1.0 pCi/gm was approximately 80 gpm. Flw readings were taken prior to the trip, after the trip, ard following plant startup on July 3, 1987.
These data points indicate that letdown flow did not change significantly during the 48 hours before the dose equivalent I-131 concentration exceeded 1.0 pCi/gm. The letdown flow history is presented in Table 3 and Figure 3.
i
: 4. Degassing Operations:    No degassing operations took place during the      l forty-eight (48) hours before the dose equivalent I-131 concentration exceeded 1.0 4Ci/gm.
: 5. Iodine sampling history: The first sample to exceed a dose equivalent I-131 concentration of 1.0 pCi/gm was a reading of 1.275 pCi/gm taken at 1542 on July 2,   1987. Approximately three (3) hours later, the dose equivalent I-131 concentration had decreased below 1.0 yCi/gm. The sample times and dose I-131 values are presented in Table 4 and Figure 4.
l

TABLE 1: REACIOR ROWER HISTORY t
DATE HOUR    %IUIL           DATE        HOUR % FULL                                            )
rmEa                             smEa                                               ;
1 6/30   1     88.88           7/2            1 86.90                                              l 2     88.79                          2 86.91 3     88.69                          3 86.86                                              l 4     88.69                          4 86.93 5     88.72                          5 86.93 6     88.70                          6 87.30 7     88.68                          7 87.74 8     88.73                          8 87.68 9     88.74                          9 87.70                                             '
10     88.16                         10 87.69 11     88.22                         11 73.07 12     88.12                         12  0.00 13     88.06                         13  0.00 14     88.09                         14  0.0J 15     88.20                         15  0.00 87.43 16                                   16  0.00 17     87.45                         17  0.00 18     87.36                         18  0.00 19     87.29                         19  0.00 20     87.24                         20  0.00 21     87.23                         21  0.00 22     87.30                         22  0.00 23     87.28                         23  0.00 24     87.36                         24  0.00 7/1    1     87.25           7/3            1  0.00 2     87.19                          2  0.00 3     87.13                          3  0.00 4     87.56                          4  0.00 5     87.75                          5  0.00 6     87.87                          6  0.00 7     87.53                          7  0.00 8     87.66                          8  0.00 9     87.80                          9  0.00 10     87.78                         10  0.00 11     87.76                         11  0.00 12     87.79                         12  0.00 13     87.75                         13  0.00 14     87.78                         14  0.00 15     87.94                         15  0.00 16     87.85                         16  0.00 17     87.26                         17  0.00 18     87.24                         18  0.00 19     87.22                         19  0.00 20     87.21                         20  0.00                                            !
21     87.20                         21  0.00                                            l 22     87.09                         22  5.12                                            l 23     87.03                         23  9.79 24     87.05                         24 11.61
_ _ _ - - - _ _ _ - - - - _ _ - - - - - - - - - - - . - _ _ - _ - - . . - - - - - - - - -           --                                                                                   )

TABIE 2
_ FUEL BMG NO.                        AVf5%GE RJRNUP l                              4                              27474 MWD /MIU 5                              26467 MWD /MIU 6A                             25678 NWD/MIU 6B                             29003 MWD /MIU l                              7A                             27984 MWD /MIU
:                              7B                             31709 MWD /M1U l                              8                              14930 MWD /MIU TABIE 3: REACIOR IETDOWN HISIORY DME            TIME                           IEIDOWN      !
GM j
6/29           0923                           77.40        !
7/2            0859                           80.02      '!'
7/3            0900                           81.32 7/3            2332                           78.28 TABIE 4: REACIOR IODINE HIS'IORY DME            TIME                           IODINE MC1/9m 6/30           0728                           0.0725 7/2             0720                          0.0650       (
7/2             1542                          1.2750         1 7/2             1857                          0.9371 7/2             2255                          0.6797 7/3             0725                          0.3980 1
                                                                                      ]
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FIGURE 2 CYCLE SIX FUEL BATCil LOCATIONS 6A   7A         7A   7A  6A 6A 7A       7A   8        6A     8 7A 7A 6A l
6B    8  7A       8    7A       8    7A  8  7A   8 6B l              6A     8     7A S        7A   8        68   8   7A 8  7A  8  6A 7A     7A    8  6A       8    7B       7A   7B  8  6A 8   7A 7A 6A 7A     8     7A 8      6B     8        4A     8 6B 8  7A  8  7A    6A i
7A 8      7A    8  7B       8  7A         7A   7A  8  7B 8   7A 8    7A 7A 6A     8     68 7A       4A 7A         4E   7A  4A 7A 6B  8  6A   7A 7A  8      7A    8  7B       8  7A         7A   7A  8  7B 8   7A 8    7A 6A  7A     8     7A 8        6B   8        4A   8   6B 8  7A  8  7A   6A 7A     7A    8  6A       8  7B         7A   7B  8  6A 8   7A 7A 6A     8     7A 8      7A   8          6B   8   7A 8  7A  8  6A 68    8  7A     8    7A       8      7A  8  7A 8   6B 6A 7A     7A   8        6A     8   7A 7A 6A 6A 7A         7A   7A  6A
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