ML19319C844
| ML19319C844 | |
| Person / Time | |
|---|---|
| Site: | Crystal River |
| Issue date: | 10/11/1977 |
| From: | FLORIDA POWER CORP. |
| To: | |
| Shared Package | |
| ML19319C838 | List: |
| References | |
| NUDOCS 8003040804 | |
| Download: ML19319C844 (3) | |
Text
.
m Technical Specification Change Request No. 11 (Appendix B)
Replace pages i and 1-3 with the attached revised pages i and 1-3.
Proposed Change Add Definition "1.16 Unplanned Release of Radioactive Material From the Site - Any release of radioactive material from the site that is not planned and contains radioactive material in quantities such that the release rate is >10% of the allowable instantaneous release rate."
Reason for the Proposal Change Specification 5.6.2.A requires a 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> report whenever any unplanned release of radioactive material from the site occurs.
Industry experience has shown that a certain amount of leakage can be expected from gaseous waste disposal system equipment.
FSAR Section 11.2.3.2 specifically addresses anticipated leaks of radioactive gases from the gaseous waste disposal system equipment.
FSAR Table 11-10 presents an estimate of the gaseous activity from releases that are r.ot planned.
At present the assumed average 45 day holdup time for leakage is not being obtained j
while the actual volume of the leakage is within the assumed 100 SCF per j
year.
Florida Power is taking steps to ensure that the gaseous waste disposal system will operate as designed with the identified holdup time.
Even so, Florida Power is striving to keep this leakage to a minimum.
Design Criterion 64 requires that "means shall be provided for monitoring... effluent discharge paths and the plant environs for radioactivity that may be released from normal operations, including anticipated operational occurrences, and from postulated accicents,"
Specification 2.4.2 provides assurance that Design Criteria 64 is met.
Unplanned releases are assumed in the FSAR and monitoring is prot ided for the effluent discharge paths; therefore amending the reporting re-quirement by adding Definition 1.16 will allow for low level unplanned releases to only be reported in the Effluent and Waste Disposal Semi-annual Report while major unplanned releases (not assumed in the FSAR) will still be a violation of a Limiting Condition for Operation and reported accordingly.
Evaluation of the Environmental Impact of the Proposed Change The proposed change concerns reporting reqJirements only and does not lessen the monitoring requirements for unplanned releases.
All unplanned releases are reported in the Effluent and Waste Dispooal Semiannual Report (combined with the batch gaseous releases) so the dose to the environment will still be determined.
Benefit - Cost Analysis of the Prooosed Change There will be no cost to the environment for the reasons stated above.
This change in reporting requirements involves low level, unplanned releases that are consistent with the assumption in the CR#3 FSAR.
The anticipated release of radioactive gases addressed in the FSAR has been reviewed and accepted by the NRC.
As these release are still monitored and result in only a small fraction of the NRC dose limits, this change is in no way detrimental to the health and safety of the public.
8008 04n f
7-)
i TABLE OF CONTENTS
'Page No.
1.0 DEFINITIONS 1.1 Frequency 1-1 1.2 Gross (B, r) Analysis
.1-1 1.3 Point of Discharge (POD) 1-1 1.4 AT Across the Condenser 1-1 1.5 Unit 3 Mixing Zone 1-1 1.6 Emergency Need for Power 1-1 1.7 Abnormal Power Operation 1-1 1.8 Known Radioactive Source 1-3 1.9 Intake Area 1-3 1.10 Discharge Area 1-3 1.11 Inner Bay 1-3 1.12 Outer Bay 1-3 1.13 Channel Calibration 1-3 1.14 Channel Check 1-3 1.15 Channel Functional Test 1-3 1.16 Unplanned Release of Radioactive Material from the Site 1-3 2.0 LIMITING CONDITIONS FOR OPERATION 2.1 Thermal 2-1 2.1.1 Maximum AT Across Condenser 2-1 2.1.2 Maximum Discharge Temperature 2-2 2.2 Hydraulic 2-3 2.3 Chemical 2-3 2.3.1 Biocides 2-3 2.3.2 Corrosion Inhibitors 2-4 2.4 Radioactive Effluents 2-4 2.4.1 Liquid Waste Effluents 2-5 2.4.2 Gaseous Waste Effluents 2-9 2.4.3 Solid Waste Handling and Disposal 2-16 3.0 ENVIRONMENTAL SURVEILLANCE 3.1 Nonradiological Surveillance 3-1
1-3 1.8-Known Radioactive Source - A calibration source which is traceable to the National Bureau of Standards radiation measurement system and is capable of reproducible geometry.
1.9 Intake Area - The i.1take canal and all of the water area south of the north intake dike and within two miles of the west tip of the south intake dike.
1.10 Discharge Area - The discharge canal and all of the water area north of the south discharge dike and within two miles of the Point of Discharge.
1.11 Inner Bay - The outer basin as shown in Figure 1.1-2 in which the planktonic ecosystem becomes as important as the bottom ecosystems.
1.13 Channel Calibration - The adjustment, as necessary, of.the channel output such that it responds with necessary range and accuracy to known values of the parameter which the channel men'. tors.
The channel calibration shall encompass the entire channel including the sensor and alarm and/or trip functions, and shall include the channel functional test.
Channel calibration may be performed by any series of sequential, overlapping or total channel steps such that-the entire channel is calibrated.
1.14 Channel Check - The qualitative assessment of channel behavior during operation by observation.
This determination shall include, where possible, comparison of the channel indication and/or status with other indications and/or status derived from independent instrument channels measuring the same parameter.
1.15 Channel Functional Test - The injection of a simulated signal into the channel as close to the primary sensor as practicable to verify operability including alcrm and/or trip functions.
1.16 Unplanned Release of Radioactive Material from the Site - Any release of radioactive material from the site that is not planned and contains radioactive material in quantities such that the release rate is n10% of the allowable instantaneous release rate.
--